Workshop on radioisotope safety issues in medical and academic institutions

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

The purpose of this workshop was to present current trends and recent initiatives of AECB staff members on issues relating to the regulation of radiation safety at hospitals and universities, and to invite the views of licencees on these matters. This report provides a record of presentations and discussions at this workshop. Presentation overheads are included as well as the results of workshop evaluations and a list of participants.

Working material. IAEA seismic safety of nuclear power plants. International workshop on lessons learned from strong earthquake

International Nuclear Information System (INIS)

2008-08-01

The International Workshop on Lessons Learned from Strong Earthquake was held at Kashiwazaki civic plaza, Kashiwazaki, Niigata-prefecture, Japan, for three days in June 2008. Kashiwazaki-Kariwa NPP (KK-NPP) is located in the city of Kashiwazaki and the village of Kariwa, and owned and operated by Tokyo Electric Power Company Ltd. (TEPCO). After it experienced the Niigata-ken Chuetsu-oki earthquake in July 2007, IAEA dispatched experts' missions twice and held technical discussions with TEPCO. Through such activities, the IAEA secretariat and experts obtained up-dated information of plant integrity, geological and seismological evaluation and developments of the consultation in the regulatory framework of Japan. Some of the information has been shared with the member states through the reports on findings and lessons learned from the missions to Japan. The international workshop was held to discuss and share the information of lessons learned from strong earthquakes in member states' nuclear installations. It provided the opportunity for participants from abroad to share the information of the recent earthquake and experience in Japan and to visit KK-NPP. And for experts in Japan, the workshop provided the opportunity to share the international approach on seismic-safety-related measures and experiences. The workshop was organised by the IAEA as a part of an extra budgetary project, in cooperation with OECD/NEA, hosted by Japanese organisations including Nuclear and Industrial Safety Agency (NISA), Nuclear Safety Commission (NSC), and Japan Nuclear Energy Safety Organization (JNES). The number of the workshop participants was 70 experts from outside Japan, 27 countries and 2 international organisations, 154 Japanese experts and 81 audience and media personnel, totalling to 305 participants. The three-day workshop was open to the media including the site visit, and covered by NHK (the nation's public broadcasting corporation) and nation-wide and local television

Advanced research workshop: nuclear materials safety

International Nuclear Information System (INIS)

Jardine, L J; Moshkov, M M.

1999-01-01

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

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

International Nuclear Information System (INIS)

Lowe, Andrew; Hayward, Brent

2006-08-01

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

International Nuclear Information System (INIS)

Wilmot, Roger D.

2011-02-01

The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety

International Nuclear Information System (INIS)

Ishigure, K.; Saeki, M.; Soda, K.; Sugimoto, J.

1992-03-01

The Third CSNI Workshop on Iodine Chemistry in Reactor Safety was held at Tokai Research Establishment of Japan Atomic Energy Research Institute at Tokai-mura, Ibaraki-ken, Japan, on September 11 to 13, 1991. About 60 experts attended the Workshop from 10 countries and 2 international organizations. In the Workshop, 29 papers were presented in five sessions on various aspects of iodine chemistry in reactor safety, such as radiolytic and surface reactions of iodine species, fundamental and integral tests, modeling and code developments. The information exchanged and the discussions followed resulted in extended and promoted understanding of iodine behavior in accidents of light water reactors and also gave a large expectation for the further progresses coming in the future. It should be emphasized that a most important and unique forum has been established through the Workshop for exchanging information and collaboratively solving the important problems in the field of the iodine chemistry in nuclear reactor safety. At the Workshop, an effort was made to integrate all information for better use by safety analysts. There is no doubt that a lot of information on iodine behaviour has been accumulated, but in many cases this information needs to be co-ordinated and well organised for safety analyses of nuclear reactors. It is essential that the results of laboratory studies and integral experiments together with modelling activities are well co-ordinated. Therefore, the goal was: - to review the knowledge and understanding of the chemistry of iodine of relevance to the prediction of its behaviour in nuclear reactors during a range of operational and accident conditions; - to define those areas of chemistry which are important but poorly understood and require further study. As shown by the conclusions of the Workshop, there is no doubt that this objective was widely attained

Developing an action-based health and safety training project in southern China.

Science.gov (United States)

Szudy, Betty; O'Rourke, Dara; Brown, Garrett D

2003-01-01

A project brought together international footwear manufacturers, labor rights groups, local contract factories, and occupational health professionals to strengthen factory health and safety programs in southern China. Steps involved in the two-year project, including needs assessment, interviews and focus groups with workers and supervisors; design and development of a participatory workshop; development of plant-wide health and safety committees in three footwear factories; and evaluation project impact, are discussed. The project significantly increased occupational safety and health knowledge, and hazards in the factories were identified and corrected. Successes and challenges faced by three functioning worker-management health and safety committees are discussed. Key elements to create effective programs with meaningful participation by workers include: 1) developing clear guidelines that enable multi-stakeholder groups to collaborate; 2) obtaining top-level management support; 3) building workers' knowledge and capacity to fully participate; 4) involving local labor rights groups and occupational professionals in support and technical assistance; and 5) connecting project goals to larger issues within a country and the global economy.

Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings

International Nuclear Information System (INIS)

Dey, M.

1993-09-01

These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission's Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements

Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Dey, M. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Arsenault, F.; Patterson, M.; Gaal, M. [SCIENTECH, Inc., Rockville, MD (United States)

1993-09-01

These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission`s Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements.

Proceedings of the first annual Nuclear Criticality Safety Technology Project

International Nuclear Information System (INIS)

Rutherford, D.A.

1994-09-01

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

Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

Energy Technology Data Exchange (ETDEWEB)

Wilmot, Roger D. (Galson Sciences Limited (United Kingdom))

2011-02-15

The workshop described here was organised to address more general issues regarding regulatory review of SKB's safety assessment and overall review strategy. The objectives of the workshop were: - to learn from other programmes' experiences on planning and review of a license application for a nuclear waste repository, - to offer newly employed SSM staff an opportunity to learn more about selected safety assessment issues, and - to identify and document recommendations and ideas for SSM's further planning of the licensing review

Proceedings of the national workshop on radiation safety and the Nigerian legal system

International Nuclear Information System (INIS)

Mallam, S.P.; Elegba, S.B.; Maiyaki, M.C.

1996-01-01

This volume is the proceedings of the National Workshop on Radiation Safety and the Nigeria Legal System held at The Centre for Energy Research and Training, Ahmadu Bello University Zaria from 7 - 9 June, 1995. The Sole aim of the workshop was to encourage the Federal Government of Nigeria to promulgate the Decree on Nuclear Safety and Radiation Protection. The focal point of the workshop was the presentation of the various peaceful applications of nuclear energy in the national economy, albeit without any legal backing. Thus there were presentations from legal practitioners. Particular consideration was given to contribution from the Agency which dealt in great details with both the legal and infra structural requirements for nuclear safety and radiation protection. Presentation by the ministry of Foreign Affairs, Federal Ministry of Health and the Federal Environmental Protection Agency underscored the multi-sectoral and multi-dimensional nature of the concern. This volume contains the full text of 11 technical papers and also speeches by invited dignitaries presented at the workshop. The papers were fully discussed during the workshop. The organizing committee wishes to thank all authors for their presentation and cooperation in submitting manuscript promptly and the participants for there excellent contribution during the workshop

The 2003 activities and the workshop of the human resources development project in FNCA

International Nuclear Information System (INIS)

2004-07-01

In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project there are two kinds of activity; In-workshop activity and Outside-of-workshop activity. The FNCA 2003 Workshop on HRD Project was held on October 8-10, 2003, in Bangkok, Thailand. The Workshop was sponsored by the Ministry of Science and Technology (MOST) of Thailand and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. Office of Atoms for Peace (OAP) and the Japan Atomic Energy Research Institute (JAERI) acted as the hosts. Participating countries were China, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. Unfortunately Indonesia could not attend the Workshop this time. This report consists of presentation papers and materials at the FNCA 2003 Workshop as In-Workshop Activity, a review document of HRD Project for the 6th Coordinators Meeting of FNCA at Tokyo on March, 2004, a letter of proposal from the Project Leader of Japan to the Project Leaders of the participating countries, and training materials of participating countries as Outside-Workshop Activity. (author)

Radiation safety in radioluminous paint workshop handling tritium activated paint

International Nuclear Information System (INIS)

Gaur, P.K.; Venkateswaran, T.V.

1986-01-01

This paper discusses the safety features related to a workshop when tritium activated luminous paint is handled by workmen. Salient features of the workshop and the methods employed for monitoring the radiation levels are briefly outlined and results are discussed. The importance of proper ventilation of the workplace and precautions to be taken in the storage of painted articles are highlighted. (author). 1 table, 3 figs

Halden Reactor Project Workshop: Understanding Advanced Instrumentation and Controls Issues

International Nuclear Information System (INIS)

Beltracchi, L.

1991-01-01

A Halden Reactor Project Workshop on 'Understanding Advanced Instrumentation and Controls Issues' was held in Halden, Norway, during June 17-18, 1991. The objectives of the workshop were to (1) identify and prioritize the types of technical information that the Halden Project can produce to facilitate the development of man-machine interface guidelines and (2) to identify methods to effectively integrate and disseminate this information to signatory organizations. As a member of the Halden Reactor Project, the Nuclear Regulatory Commission (NRC) requested the workshop. This request resulted from the NRC's need for human factors guidelines for the evaluation of advanced instrumentation and controls. The Halden Reactor Project is a cooperative agreement among several countries belonging to the Organization for Economic Cooperation and Development (OECD). The US began its association with the Halden Project in 1958 through the Atomic Energy Commission. The project's activities are centered at the Halden heavy-water reactor and its associated man-machine laboratory in Halden, Norway. The research program conducted at Halden consists of studies on fuel performance and computer-based man-machine interfaces

N Reactor Lessons Learned workshop

International Nuclear Information System (INIS)

Heaberlin, S.W.

1993-07-01

This report describes a workshop designed to introduce participants to a process, or model, for adapting LWR Safety Standards and Analysis Methods for use on rector designs significantly different than LWR. The focus of the workshop is on the ''Lessons Learned'' from the multi-year experience in the operation of N Reactor and the efforts to adapt the safety standards developed for commercial light water reactors to a graphite moderated, water cooled, channel type reactor. It must be recognized that the objective of the workshop is to introduce the participants to the operation of a non-LWR in a LWR regulatory world. The total scope of this topic would take weeks to provide a through overview. The objective of this workshop is to provide an introduction and hopefully establish a means to develop a longer term dialogue for technical exchange. This report provides outline of the workshop, a proposed schedule of the workshop, and a description of the tasks will be required to achieve successful completion of the project

78 FR 32010 - Pipeline Safety: Public Workshop on Integrity Verification Process

Science.gov (United States)

2013-05-28

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Hazardous Materials Safety Administration, DOT. ACTION: Notice of public meeting. SUMMARY: This notice is announcing a public workshop to be held on the concept of ``Integrity Verification Process.'' The Integrity...

1. annual workshop proceedings of integrated project fundamental processes of radionuclide migration IP Funmig

International Nuclear Information System (INIS)

Reiller, P.; Buckau, G.; Kienzler, B.; Duro, L.; Martell, M.

2006-01-01

These are the proceedings of the 1. Annual Workshop Proceedings of the Integrated Project FUNMIG (fundamental processes of radionuclide migration). The Annual Workshop was hosted by CEA and held in Saclay, 28 November - 1 December 2005. The project started January 2005 and has a duration of four years. The project makes use of annual workshops bringing the project partners together and inviting external groups to participate and contribute. Consequently, the present proceedings will be followed by another three proceedings from the forthcoming annual workshops to be held the end of 2006, 2007 and 2008. The 2. Annual Workshop will be hosted by SKB and be held in Stockholm, 21-23 November 2006. The proceedings serve several purposes. The key purpose is to document and make available to a broad scientific community the outcome of this project. A considerable part of the project activity reporting is also done through the proceedings. For this reason the first parts of the proceedings are structured around the workshop and the project. A large part of the proceedings, however, also contain individual scientific contributions by the project partners as well as external contributors. Information about the project can be found under www.funmig.com. (authors)

Workshop on development and view on digital safety system of KNICS

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-05-15

The contents of this workshop are vision of KNICS, introduction of development of safety system of KNICS, development situation of safety class of PLC, view of software for safety-critical system in PLC, RTOS development by shaping, quality assurance and attestation of PLC, development situation of nuclear reactor system and development situation of ESF-CCS.

Workshop on development and view on digital safety system of KNICS

International Nuclear Information System (INIS)

2006-05-01

The contents of this workshop are vision of KNICS, introduction of development of safety system of KNICS, development situation of safety class of PLC, view of software for safety-critical system in PLC, RTOS development by shaping, quality assurance and attestation of PLC, development situation of nuclear reactor system and development situation of ESF-CCS

Second ANS workshop on the safety of Soviet-designed nuclear power plants. Summary report

International Nuclear Information System (INIS)

Bari, R.A.

1995-03-01

The Second American Nuclear Society Workshop on the Safety of Soviet-Designed Nuclear Power Plants was held in Washington, DC, in November, 1994. The Workshop consisted of both plenary sessions and working sessions with three hundred participants overall. All countries with operating Soviet-Designed nuclear power plants were represented and representatives from several other countries also participated. In addition to the status and plans related to technical issues, the Workshop also included discussions of economic, political, legal, and social issues as they relate to the safety of these nuclear power plants

The Halden Reactor Project workshop on HAMMLAB 2000

International Nuclear Information System (INIS)

Sebok, Angelia L.; Grini, Rolf-Einar; Larsen, Marit; Ness, Eyvind; Soerensen, Aimar

1998-01-01

A workshop on HAMMLAB 2000 was organised in Halden, May 26-27, 1997. The purpose of the workshop was to discuss and make recommendations on requirements for the design of HAMMLAB 2000 and to discuss the future research agenda. The workshop began with several presentations summarising the status of the current HAMMLAB 2000 project. Three invited speakers with expertise in human-machine laboratories and simulators delivered presentations of their experiences. Later, the workshop was divided into five working groups that discussed the following issues in parallel: (1) Technical Studies, Research Agenda; (2) Human Factors Research Agenda; (3) Data Collection; (4) Synergy with Other Industries; (5) Virtual Reality. Each group produced specific recommendations that were summarised by the group's facilitator in a joint session of the workshop. This report summarises the presentation of the invited speakers, and the discussions and recommendations of the individual working groups. (author)

Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety

Energy Technology Data Exchange (ETDEWEB)

Guentay, S [ed.; Paul Scherrer Inst. (PSI), Villigen (Switzerland)

1996-12-01

The 4. OECD workshop on the chemistry of iodine in reactor safety was held in Wuerenlingen, Switzerland from June 10th to 12th, 1996. It was organised in collaboration with the Laboratory for Safety and Accident Research of the Paul Scherrer Institute. About seventy experts from fourteen OECD member countries attended the meeting, as well as experts from Latvia and the Commission of the European Communities. Thirty-four papers were presented in five sessions on various aspects of national and international programmes, integral and intermediate-scale experiments, experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies and safety applications. Throughout the meeting, emphasis was placed on detailed and open discussions. The purpose of the workshop was to exchange information on the iodine chemistry and other important fission products relevant to reactor safety, to discuss the status of the open issues identified during the previous workshop held in 1991, to define reactor safety issues and to discuss developments and future plans. (author) figs., tabs., refs.

Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety

International Nuclear Information System (INIS)

Guentay, S.

1996-12-01

The 4. OECD workshop on the chemistry of iodine in reactor safety was held in Wuerenlingen, Switzerland from June 10th to 12th, 1996. It was organised in collaboration with the Laboratory for Safety and Accident Research of the Paul Scherrer Institute. About seventy experts from fourteen OECD member countries attended the meeting, as well as experts from Latvia and the Commission of the European Communities. Thirty-four papers were presented in five sessions on various aspects of national and international programmes, integral and intermediate-scale experiments, experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies and safety applications. Throughout the meeting, emphasis was placed on detailed and open discussions. The purpose of the workshop was to exchange information on the iodine chemistry and other important fission products relevant to reactor safety, to discuss the status of the open issues identified during the previous workshop held in 1991, to define reactor safety issues and to discuss developments and future plans. (author) figs., tabs., refs

Workshop to review problem-behavior research programs : pedestrian, bicycle, and pupil transportation safety

Science.gov (United States)

1981-09-01

This report presents the proceedings of a workshop on pedestrian, bicycle, and pupil transportation safety. The purpose of this workshop was to develop specific recommendations for the planning and implementation of NHTSA research, development, and d...

Proceedings of the third CSNI workshop on iodine chemistry in reactor safety

International Nuclear Information System (INIS)

Ishigure, Kenkichi; Saeki, Masakatsu; Soda, Kunihisa; Sugimoto, Jun

1992-03-01

This issue is the collection of the papers presented at the CSNI (Committee on the Safety of Nuclear Installations) workshop on iodine chemistry in reactor safety. The 31 of the presented papers are indexed individually. (J.P.N.)

European Workshop Industrical Computer Science Systems approach to design for safety

Science.gov (United States)

Zalewski, Janusz

1992-01-01

This paper presents guidelines on designing systems for safety, developed by the Technical Committee 7 on Reliability and Safety of the European Workshop on Industrial Computer Systems. The focus is on complementing the traditional development process by adding the following four steps: (1) overall safety analysis; (2) analysis of the functional specifications; (3) designing for safety; (4) validation of design. Quantitative assessment of safety is possible by means of a modular questionnaire covering various aspects of the major stages of system development.

Proceedings of the workshops on 'JAEA project researches at J-PARC/MLF'

International Nuclear Information System (INIS)

Kajimoto, Ryoichi; Maekawa, Fujio; Arima, Hiroshi; Yoshinari, Shizuka; Arai, Masatoshi

2011-06-01

The operation for public use of Materials and Life Science Experimental Facility (MLF) at Japan Proton Accelerator Research Complex (J-PARC) has started since the end of 2008. Rather stable neutron and muon beams at 120 kW are being supplied throughout 2010. Some of the instruments have already produced several good scientific outputs. Furthermore, operation at 200 kW, which exceeds the beam power of the ISIS facility in UK, has started since December 2010. In this promising situation for MLF, we hold three workshops for five neutron instruments which conducted researches for projects by Japan Atomic Energy Agency (JAEA) (project researches): 'Workshop on BL19 (Sep. 29)', 'Workshop on BL04+BL10 (Oct. 28)', and 'Workshop on BL01+BL14 (Oct. 29)'. There, status of the instruments and recent results of the project researches as well as a part of researches by general users were reported, and future directions and issues to be solved of the researches were discussed. This report includes abstracts, materials of the presentations and summary of discussions in the workshops. (author)

Workshop on Indian Chemical Industry: perspectives on safety, cleaner production and environment production

NARCIS (Netherlands)

Ham, J.M.

1996-01-01

A Workshop on "Indian Chemical Industry: Perspectives on Safety, Cleaner Production and Environmental Protection" was held on 3, 4 and 5 January 1996, in Bombay, India. The main objective of the workshop, which was organised jointly by the Government of India, UNIDO/UNDP and the Indian Chemical

Scenario Development Workshop Synopsis. Integration Group for the Safety Case - June 2015

International Nuclear Information System (INIS)

Smith, Paul; Voinis, Sylvie; Griffault, Lise; De Meredieu, Jean; Kwong, Gloria; ); Van Luik, Abraham; Bailey, Lucy; Capouet, Manuel; Depaus, Christophe; Makino, Hitoshi; Leigh, Christi; Kirkes, Ross; Leino, Jaakko; Niemeyer, Matthias; Wolf, Jens; Watson, Sarah; Franke, Bettina; Ilett, Doug; Pastina, Barbara; Weetjens, Eef

2016-03-01

Scenario development and selection describes the collection and organisation of the scientific and technical information relevant to the potential paths of evolution of a radioactive waste disposal facility (repository) that is necessary to assess its long-term performance and safety. In 1999, the NEA held its first workshop on scenario development in Madrid, Spain, with the objective to review the methods for developing scenarios in safety assessments and their application. Since then, the process of scenario development and analysis for the disposal of radioactive waste has changed and, in 2015, the NEA Integration Group for the Safety Case (IGSC) held a second workshop on this topic at its offices in Paris to further evaluate the experience acquired in developing scenarios since 1999. To prepare for this workshop, the IGSC also launched a survey in 2014 to gather the latest scenario development and uncertainty management strategies used in IGSC member countries. The purposes of the workshop were to (i) provide a forum to review and discuss methods for scenario development and their contribution to the development of recent safety cases (since the 1999 workshop); (ii) examine the latest methods and compare their scope, consistency and function within the overall safety assessment process, based on practical experience of applications; and (iii) provide a basis for producing the present report summarising the current status of scenario methodologies, identifying where sufficient methods exist and any outstanding problem areas. This report provides an overview of the state of the art in scenario development related to the long-term safety of geological repositories for radioactive waste. In particular, it discusses how potential scenarios are developed in safety assessments of radioactive waste that contains long-lived radionuclides. Safety assessment is the process of quantitatively and qualitatively evaluating the safety of a repository, often in support of a

Applying the systems engineering approach to video over IP projects : workshop.

Science.gov (United States)

2011-12-01

In 2009, the Texas Transportation Institute produced for the Texas Department of Transportation a document : called Video over IP Design Guidebook. This report summarizes an implementation of that project in the : form of a workshop. The workshop was...

75 FR 13342 - Pipeline Safety: Workshop on Distribution Pipeline Construction

Science.gov (United States)

2010-03-19

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID... natural gas distribution construction. Natural gas distribution pipelines are subject to a unique subset... distribution pipeline construction practices. This workshop will focus solely on natural gas distribution...

Workshop on a project for a FZR-beam line at ESRF

International Nuclear Information System (INIS)

Matz, W.

1993-10-01

The Research Center Rossendorf (FZR) investigates the possibilities to install its own beam line as a Cooperate Research Group-project (CRG) at the European Synchrotron Radiation Facility (ESRF) in Grenoble. The main interests for the FZR to use high brillant synchrotron radiation are in the Institute of Radiochemistry and the Institute of Ion Beam Physics and Materials Research. This workshop was organized by these two institutes together with the FZR Study group Synchrotron. The purpose of the workshop was to achieve a better understanding for the technical needs of the projected beam line for the planned research projects. Experts with experience in beam line design met with the Rossendorf groups to discuss the best layout for such a beam line. The summary of this workshop and the copies of transparencies of the lectures that were given are published in this booklet. (orig.)

The 2002 activities and the 4th workshop of the human resources development project in FNCA

International Nuclear Information System (INIS)

2003-07-01

In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project there are two kinds of activity; In-workshop activity and Outside-of-workshop activity. The 4th Workshop on HRD Project was held on october 8-10, 2002, in Batangas, the Philippines. The Workshop was sponsored by the Department of Science and Technology (DOST) of the Philippines and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The Philippine Nuclear Research Institute (PNRI) and the Japan Atomic Energy Research Institute (JAERI) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Phillippines, Thailand, and Vietnam. This report consists of presentation papers and materials at the 4th workshop as In-Workshop Activity, a review document of HRD Project for the 5th Coordinators Meeting of FNCA at Tokyo on March, 2003, a letter of proposal from the Project Leader of Japan to the Project Leaders of the participating countries, and training materials of participating countries as Outside-Workshop Activity. (author)

Proceedings of the Task 2 workshop Waste Isolation Safety Assessment Program

International Nuclear Information System (INIS)

Bradley, D.J.

1979-01-01

The reports from the workshop on waste form release rate analysis are presented. The workshop started with overview presentations on the Office of Nuclear Waste Isolation (ONWI), the Waste Isolation Safety Assessment Program (WISAP), WISAP Task 2 (Waste Form Release Rate Analysis), and WISAP Task 4 (Sorption/Desorption Analysis). Technical presentations followed in these areas: leaching studies on spent fuels, leaching studies on high-level waste glass, waste form surface science experiments, radiation effects, and leach modeling. Separate abstracts were prepared for each

Proceedings of the Task 2 workshop Waste Isolation Safety Assessment Program

Energy Technology Data Exchange (ETDEWEB)

Bradley, D.J.

1979-01-01

The reports from the workshop on waste form release rate analysis are presented. The workshop started with overview presentations on the Office of Nuclear Waste Isolation (ONWI), the Waste Isolation Safety Assessment Program (WISAP), WISAP Task 2 (Waste Form Release Rate Analysis), and WISAP Task 4 (Sorption/Desorption Analysis). Technical presentations followed in these areas: leaching studies on spent fuels, leaching studies on high-level waste glass, waste form surface science experiments, radiation effects, and leach modeling. Separate abstracts were prepared for each.

IAEA/USDOE senior management workshop on promotion of safety culture for the NPPS with RBMK reactors. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

The current workshop, co-sponsored by the IAEA and USDOE, was a continuation of the previous effort for further promotion of safety culture at RBMK NPPs. The objective of the workshop was to provide a forum for senior managers from governmental organizations and operating organizations to further exchange experience in understanding the factors influencing safety culture, in assessing safety culture at their own organizations and developing safety culture at RBMK NPPs. The workshop consisted of a broad scope of presentations to review the basic concepts and major elements of safety culture (ownership, accountability, pride, job satisfaction, trust, openness, etc.), to identify and discuss the various approaches used in different countries in attaining a strong safety culture, and to explain, through the use of practical examples, what the benefits of a strong safety culture are; how to improve the behavior of people, how to gain trust and openness, how to overcome difficulties in changing staff`s attitudes, and how to manage safety culture. 2 figs.

IAEA/USDOE senior management workshop on promotion of safety culture for the NPPS with RBMK reactors. Working material

International Nuclear Information System (INIS)

1997-01-01

The current workshop, co-sponsored by the IAEA and USDOE, was a continuation of the previous effort for further promotion of safety culture at RBMK NPPs. The objective of the workshop was to provide a forum for senior managers from governmental organizations and operating organizations to further exchange experience in understanding the factors influencing safety culture, in assessing safety culture at their own organizations and developing safety culture at RBMK NPPs. The workshop consisted of a broad scope of presentations to review the basic concepts and major elements of safety culture (ownership, accountability, pride, job satisfaction, trust, openness, etc.), to identify and discuss the various approaches used in different countries in attaining a strong safety culture, and to explain, through the use of practical examples, what the benefits of a strong safety culture are; how to improve the behavior of people, how to gain trust and openness, how to overcome difficulties in changing staff's attitudes, and how to manage safety culture. 2 figs

IAEA TC Project 'Strengthening safety and reliability of fuel and materials in nuclear power plants'

International Nuclear Information System (INIS)

Makihara, Y.

2008-01-01

The Regional TC Project in Europe RER9076 'Strengthening Safety and Reliability of Fuel and Materials in Nuclear Power Plants' was launched in 2003 as a four-year project and was subsequently extended in 2006 to run through 2008. The purpose of the Project is to support the Central and Eastern European countries with the necessary tools to fulfill their own fuel and material licensing needs. The main objective will be to provide quality data on fuel and materials irradiated in power reactors and in dedicated experiments carried out in material test reactors (MTRs). Within the framework of the Project, ten tasks were implemented. These included experiments performed at the test facilities in the region, training courses and workshops related to fuel safety. While several tasks are expected to be completed by the end of RER9076, some remain. It would be desirable to initiate a new RER Project from the next TC cycle (2009-2011) in order to take over RER9076 and to implement new tasks required for enhancing fuel safety in the region. (author)

The 2006 activities and the workshop of the human resources development project in FNCA (Contract research)

International Nuclear Information System (INIS)

2007-09-01

In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asia countries. In the Project there are two kinds of activity; In-workshop activity and Outside-workshop activity. The FNCA 2006 Workshop on HRD Project was held on July 31 - August 4, 2006, in Shenzhen, China. The Workshop was sponsored by the China Atomic Energy Authority (CAEA) and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The China Atomic Energy Authority (CAEA) and the Japan Atomic Energy Agency (JAEA) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The activities of HRD Project was presented in the Eighth Coordinators Meeting of FNCA held on February 7th - 9th, 2007, in Tokyo, Japan. This report consists of presentation papers and materials at the FNCA 2006 Workshop, a review document of HRD Project for the Coordinators Meeting of FNCA as Outside-Workshop Activity. (author)

The 2005 activities and the workshop of the human resources development project in FNCA (Contract research)

International Nuclear Information System (INIS)

2006-10-01

In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project there are two kinds of activity; In-workshop activity and Outside-of-workshop activity. The FNCA 2005 Workshop on HRD Project was held on September 13-16, 2005, in Dalat, Viet Nam. The Workshop was sponsored by the Ministry of Science and Technology (MOST) of Viet Nam and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The Vietnam Atomic Energy Commission (VAEC) and the Japan Atomic Energy Agency (JAEA) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The activities of HRD Project was presented in the Seventh Coordinators Meeting of FNCA was held on March 30 - April 1, 2006, in Tokyo, Japan. This report consists of presentation papers and materials at the FNCA 2005 Workshop, a review document of HRD Project for the Coordinators Meeting of FNCA as Outside-Workshop Activity. (author)

78 FR 30964 - Pipeline Safety: Workshop on Public Awareness Programs

Science.gov (United States)

2013-05-23

... Richardson, Texas. The workshop serves as an opportunity to bring pipeline safety stakeholders together to..., and excavators) will share their perspectives on what is working and what is not working with existing... discuss recent inspection findings; (2) Understand what's working and not working with public awareness...

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

International Nuclear Information System (INIS)

Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

1997-01-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

Energy Technology Data Exchange (ETDEWEB)

Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

1997-07-01

The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

The 2004 activities and the workshop of the human resources development project in FNCA. Contract research

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-08-01

In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project there are two kinds of activity; in-workshop activity and Outside-of-workshop activity. The FNCA 2004 Workshop on HRD Project was held on October 4-7, 2004, in Kuala Lumpur, Malaysia. The Workshop was sponsored by the Ministry of Science and Technology Innovation (MOSTI) of Malaysia and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The Malaysian Institute for Nuclear Technology Research (MINT) and the Japan Atomic Energy Research Institute (JAERI) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The activities of HRD Project was presented in the Sixth Coordinators Meeting of FNCA was held on March 30 - April 1, 2005, in Tokyo, Japan. This report consists of presentation papers and materials at the FNCA 2004 Workshop, a review document of HRD Project for the Coordinators Meeting of FNCA, a letter of request from the Project Leader of Japan to the Project Leaders of the participating countries and theme of the country report as Outside-Workshop Activity. (author)

The 2001 activities and the 3rd workshop of the human resources development project in FNCA

International Nuclear Information System (INIS)

2002-07-01

In 1999, the Project for Human Resources Development (HRD) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project are two kinds of activity; In-workshop activity and Outside-of-workshop activity. The 3rd Workshop on Human Resources Development in the Nuclear Field was held on October 29 to November 1, at the Nuclear Training Center of KAERI. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The secretariat for the Human Resources Development Project is provided by the Nuclear Training Center of the Korea Atomic Energy Research Institute and the Nuclear Technology and Education Center of the Japan Atomic Energy Research Institute. This report consists of presentation papers and materials at the Workshop as In-Workshop Activity, a document of project review on Human Resources Development for the fourth Coordinators Meeting of FNCA at Tokyo on March, 2002, a letter of proposal from the Project Leader of Japan to the project leaders of the participating countries, and training materials of participating countries as Outside-Workshop Activity. (author)

75 FR 15485 - Pipeline Safety: Workshop on Guidelines for Integrity Assessment of Cased Pipe

Science.gov (United States)

2010-03-29

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID...: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of workshop. SUMMARY... ``Guidelines for Integrity Assessment of Cased Pipe in Gas Transmission Pipelines'' and related Frequently...

1. annual workshop proceedings of integrated project fundamental processes of radionuclide migration IP Funmig; Rapport du 1. workshop annuel du projet integre fundamental processes of radionuclide migration (IP Funmig)

Energy Technology Data Exchange (ETDEWEB)

Reiller, P [CEA Saclay, Dept. de Physico-Chimie (DPC), 91 - Gif sur Yvette (France); Buckau, G; Kienzler, B [Institut fur Nukleare Entsorgung (INE), Karlsruhe (Germany); Duro, L; Martell, M [Enviros (Spain)

2006-07-01

These are the proceedings of the 1. Annual Workshop Proceedings of the Integrated Project FUNMIG (fundamental processes of radionuclide migration). The Annual Workshop was hosted by CEA and held in Saclay, 28 November - 1 December 2005. The project started January 2005 and has a duration of four years. The project makes use of annual workshops bringing the project partners together and inviting external groups to participate and contribute. Consequently, the present proceedings will be followed by another three proceedings from the forthcoming annual workshops to be held the end of 2006, 2007 and 2008. The 2. Annual Workshop will be hosted by SKB and be held in Stockholm, 21-23 November 2006. The proceedings serve several purposes. The key purpose is to document and make available to a broad scientific community the outcome of this project. A considerable part of the project activity reporting is also done through the proceedings. For this reason the first parts of the proceedings are structured around the workshop and the project. A large part of the proceedings, however, also contain individual scientific contributions by the project partners as well as external contributors. Information about the project can be found under www.funmig.com. (authors)

Fusion Simulation Project Workshop Report

Science.gov (United States)

Kritz, Arnold; Keyes, David

2009-03-01

The mission of the Fusion Simulation Project is to develop a predictive capability for the integrated modeling of magnetically confined plasmas. This FSP report adds to the previous activities that defined an approach to integrated modeling in magnetic fusion. These previous activities included a Fusion Energy Sciences Advisory Committee panel that was charged to study integrated simulation in 2002. The report of that panel [Journal of Fusion Energy 20, 135 (2001)] recommended the prompt initiation of a Fusion Simulation Project. In 2003, the Office of Fusion Energy Sciences formed a steering committee that developed a project vision, roadmap, and governance concepts [Journal of Fusion Energy 23, 1 (2004)]. The current FSP planning effort involved 46 physicists, applied mathematicians and computer scientists, from 21 institutions, formed into four panels and a coordinating committee. These panels were constituted to consider: Status of Physics Components, Required Computational and Applied Mathematics Tools, Integration and Management of Code Components, and Project Structure and Management. The ideas, reported here, are the products of these panels, working together over several months and culminating in a 3-day workshop in May 2007.

International shock-wave database project : report of the requirements workshop.

Energy Technology Data Exchange (ETDEWEB)

Aidun, John Bahram (Institute of Problems of chemical Physics of Russian Academy of Sciences); Lomonosov, Igor V. (Institute of Problems of chemical Physics of Russian Academy of Sciences); Levashov, Pavel R. (Joint Institute for High Temperatures of Russian Academy of Sciences)

2012-03-01

We report on the requirements workshop for a new project, the International Shock-Wave database (ISWdb), which was held October 31 - November 2, 2011, at GSI, Darmstadt, Germany. Participants considered the idea of this database, its structure, technical requirements, content, and principles of operation. This report presents the consensus conclusions from the workshop, key discussion points, and the goals and plan for near-term and intermediate-term development of the ISWdb. The main points of consensus from the workshop were: (1) This international database is of interest and of practical use for the shock-wave and high pressure physics communities; (2) Intermediate state information and off-Hugoniot information is important and should be included in ISWdb; (3) Other relevant high pressure and auxiliary data should be included to the database, in the future; (4) Information on the ISWdb needs to be communicated, broadly, to the research community; and (5) Operating structure will consist of an Advisory Board, subject-matter expert Moderators to vet submitted data, and the database Project Team. This brief report is intended to inform the shock-wave research community and interested funding agencies about the project, as its success, ultimately, depends on both of these groups finding sufficient value in the database to use it, contribute to it, and support it.

EC-funded project (HTR-L) for the definition of a European safety approach for HTR's

International Nuclear Information System (INIS)

Ehster, S.; Dominguez, M.T.; Coe, I.; Brinkmann, G.; Lensa, W. von; Mheen, W. van der; Alessandroni, C.; Pirson, J.

2002-01-01

The inherent safety features of the HTRs make events leading to severe core damage highly unlikely and constitute the main differentiating aspects compared to LWRs. While a known and stable regulatory environment has long been established for Light Water Reactors, a different approach is necessary for the licensing of HTR based power plants. Among the R and D projects funded by the European Commission for HTR reactors, the HTR-L project is dedicated to the definition of a common and coherent European safety approach and the identification of the main licensing issues for the licensing framework of the Modular HTRs. Other specific objectives of this project are : To develop a methodology to classify the accidental conditions; To define the preliminary requirements for the confinement of radioactive products and to assess the need for a 'conventional' containment structure; To establish a SSC (2) classification and to define the rules for equipment qualification; To identify the key issues that need to be addressed in the licensing process of the HTRs; To organize a workshop with the concerned Safety Authorities at the end of the project. This paper will explain the project objectives and its final expected outcomes. (author)

OECD/NEA WGFCS Workshop: Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives

International Nuclear Information System (INIS)

2013-01-01

Nuclear fuel is produced, processed, and stored mainly in industrial-scale facilities. Uranium ores are processed and refined to produce a pure uranium salt stream, Uranium is converted and enriched, nuclear fuel is fabricated (U fuel and U/Pu fuel for the closed cycle option); and spent fuel is stored and reprocessed in some countries (close cycle option). Facilities dedicated to the research and development of new fuel or new processes are also considered as Fuel Cycle Facilities. The safety assessment of nuclear facilities has often been led by the methodology and techniques initially developed for Nuclear Power Plants. As FCFs cover a wide diversity of installations the various approaches of national regulators, and their technical support organizations, for the Safety Assessment of Fuel Cycle Facilities are also diverse, as are the approaches by their industries in providing safety justifications for their facilities. The objective of the Working Group on Fuel Cycle Safety is to advance the understanding for both regulators and operators of relevant aspects of nuclear fuel cycle safety in member countries. A large amount of experience is available in safety assessment of FCFs, which should be shared to develop ideas in this field. To contribute to this task, the Workshop on 'Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives' was held in Toronto, on 27 - 29 September 2011. The workshop was hosted by Canadian Nuclear Safety Commission. The current proceedings provide summary of the results of the workshop with the text of the papers given and presentations made

The Chemistry of iodine in reactor safety: summary and conclusions: OECD Workshop

International Nuclear Information System (INIS)

1996-01-01

About seventy experts from fourteen OECD member countries attended this Fourth OECD Workshop on the chemistry of iodine in reactor safety, as well as experts from Latvia and the Commission of the European Communities. Thirty four papers were presented, in five sessions: national and international programmes (integral and intermediate-scale experiments), experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies, safety applications. A final session is devoted to a general discussion on remaining research studies relevant to reactor safety

78 FR 10181 - Global Quality Systems-An Integrated Approach To Improving Medical Product Safety; Public Workshop

Science.gov (United States)

2013-02-13

...] Global Quality Systems--An Integrated Approach To Improving Medical Product Safety; Public Workshop... (AFDO), is announcing a public workshop entitled ``Global Quality Systems--An Integrated Approach to... topics concerning FDA requirements related to the production and marketing of drugs and/or devices...

2012 national state safety engineers and traffic engineers peer-to-peer workshop.

Science.gov (United States)

2013-11-01

The Illinois Department of Transportation (IDOT) and the Illinois Center for Transportation (ICT) sponsored and hosted the : 2012 National State Safety Engineers and Traffic Engineers Peer-to-Peer Workshop on November 14 and 15, 2012, at the : Hyatt ...

Oversight and Influencing of Licensee Leadership and Management for Safety, Including Safety Culture - Regulatory Approaches and Methods. Proceedings of an NEA/IAEA Workshop, Chester, United Kingdom, 26-28 September 2011

International Nuclear Information System (INIS)

2012-01-01

Both regulators and the nuclear industry recognise the need for licensees to develop a strong, positive safety culture to support successful and sustainable nuclear safety performance. A number of reports have been issued by the IAEA and the NEA on the role of the regulator in relation to oversight of safety culture (References 1 to 5). There has been less clarity on how this should be achieved - in particular, with regard to strategies and practical approaches for maintaining oversight of, and influencing, those facets of licensee leadership and management which have a profound influence on safety culture. In recognition of this, the CSNI Working Group on Human and Organisational Factors (WGHOF), together with the CNRA Working Group on Inspection Practices (WGIP) and the IAEA, organised a workshop in Chester, United Kingdom, in May 2007 to provide a forum for gathering and sharing international experience, including good practices and learning points. The results of the workshop are reported in Reference 6. Workshop participants agreed that, in view of the rapidly developing approaches in this area, it would be sensible to hold a further workshop ('Chester 2') in 3-5 years in order to discuss how regulatory approaches have moved on and to share lessons learned from their application. In 2010, the WGIP hosted a workshop which included regulatory approaches for the assessment of licensee safety culture as a discussion topic. The outputs of the workshop included a list of commendable practices for monitoring and evaluating licensee safety culture (Reference 7). The 'Chester 2' workshop took place in September 2011. This report sets out the findings of the workshop, organised by the UK Office for Nuclear Regulation (ONR) on behalf of the CSNI/WGHOF and the IAEA. The workshop was attended by over 40 representatives of nuclear regulatory bodies and licensees from 15 countries plus IAEA and NEA. The workshop featured keynote papers on learning from major events, and from

Proceedings of the Nuclear Criticality Technology Safety Workshop

Energy Technology Data Exchange (ETDEWEB)

Rene G. Sanchez

1998-04-01

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

75 FR 20009 - Development of NRC's Safety Culture Policy Statement: Cancellation of Public Workshops Scheduled...

Science.gov (United States)

2010-04-16

... included the development of the safety culture common terminology effort comprised of: (1) Development of a... alignment on the safety culture common terminology effort. The NRC held the first workshop on February 2-4... of individual industry groups, such as, [[Page 20010

Supporting research projects via student workshops

DEFF Research Database (Denmark)

Marschall, Max; Schmeck, Michel; Gengnagel, Christoph

2016-01-01

As part of a joint research project between the Centre for Information Technology and Architecture (CITA) and te Department for Structural Design and Technology (KET), a one week student workshop was organised at the Royal Danish Academy of Fine Arts (KADK) in Copenhagen. This paper outlines...... the teaching methods applied to reach maximum insight from student interaction, despite the unfamiliarity the students had with the research matter: physical and numeric form-finding for lightweight hybrid structures. Hybrid structures are defined here as combining different components of low stiffness...

A First Implementation of a Design Thinking Workshop During a Mobile App Development Project Course

OpenAIRE

Pham, Yen Dieu; Fucci, Davide; Maalej, Walid

2018-01-01

Due to their characteristics, millennials prefer learning-by-doing and social learning, such as project-based learning. However, software development projects require not only technical skills but also creativity; Design Thinking can serve such purpose. We conducted a workshop following the Design Thinking approach of the d.school, to help students generating ideas for a mobile app development project course. On top of the details for implementing the workshop, we report our observations, les...

Proceedings of the CSNI WGOE/SEGHOF workshop on modifications at nuclear power plants - Operating experience, safety significance and the role of human factors and organisation

International Nuclear Information System (INIS)

2004-01-01

Operating experience repeatedly shows that changes and modifications at nuclear power plants (NPPs) may lead to safety significant events. At the same time, modifications are necessary to ensure a safe and economic functioning of the NPPs. To ensure the continuing safety of NPPs it is important that processes for change and modification are given proper attention both by the NPPs and the regulators. The operability, maintainability and testability of every modification should be thoroughly assessed from different points of view to ensure that no safety problems are introduced. The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) addressed the issue of modifications at a 'Workshop on Modifications at Nuclear Power Plants - Operating Experience, Safety Significance and Role of Human Factors' held at the OECD headquarters in Paris on October 6 to 8, 2003. This workshop was undertaken as a joint effort of the Working Group on Operating Experience (WGOE) and the Special Experts Group on Human and Organisational Factors (SEGHOF). During the workshop, WGOE focused on the theme of 'Minor Modifications and their Safety Significance', while SEGHOF focused on the topic 'Human and Organisational Factors in NPP Modifications'. The workshop was attended by 55 experts from the industry, regulators and technical support organizations in 15 countries. The workshop programme consisted of plenary and parallel sessions for presentations and discussions. One important part of the workshop was to discuss findings of the WGOE and SEGHOF surveys of utility and regulatory experience from modifications at the NPPs. Modifications at the NPPs are controlled by written procedures. The process varies depending on the type of the modification. Large modifications generally lead to fewer problems, because the projects are given both a great deal of attention and resources. In contrast, minor modifications seem to represent a generic challenge because they are less likely to be

International Workshop on Characterization and PIE Needs for Fundamental Understanding of Fuels Performance and Safety

Energy Technology Data Exchange (ETDEWEB)

Not Listed

2011-12-01

The International Workshop on Characterization and PIE Needs to Support Science-Based Development of Innovative Fuels was held June 16-17, 2011, in Paris, France. The Organization for Economic Co-operation and Development (OECD), Nuclear Energy Agency (NEA) Working Party on the Fuel Cycle (WPFC) sponsored the workshop to identify gaps in global capabilities that need to be filled to meet projected needs in the 21st century. First and foremost, the workshop brought nine countries and associated international organizations, together in support of common needs for nuclear fuels and materials testing, characterization, PIE, and modeling capabilities. Finland, France, Germany, Republic of Korea, Russian Federation, Sweden, Switzerland, United Kingdom, United States of America, IAEA, and ITU (on behalf of European Union Joint Research Centers) discussed issues and opportunities for future technical advancements and collaborations. Second, the presentations provided a base level of understanding of current international capabilities. Three main categories were covered: (1) status of facilities and near term plans, (2) PIE needs from fuels engineering and material science perspectives, and (3) novel PIE techniques being developed to meet the needs. The International presentations provided valuable data consistent with the outcome of the National Workshop held in March 2011. Finally, the panel discussion on 21st century PIE capabilities, created a unified approach for future collaborations. In conclusion, (1) existing capabilities are not sufficient to meet the needs of a science-based approach, (2) safety issues and fuels behavior during abnormal conditions will receive more focus post-Fukushima; therefore we need to adopt our techniques to those issues, and (3) International collaboration is needed in the areas of codes and standards development for the new techniques.

Nuclear safety project

International Nuclear Information System (INIS)

1982-06-01

The Annual Report 1981 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1981 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on - work completed - results obtained - plans for future work. This report was compiled by the project management. (orig.) [de

Cementitious Materials in Safety Cases for Geological Repositories for Radioactive Waste: Role, Evolution and Interactions. A Workshop organised by the OECD/NEA Integration Group for the Safety Case and hosted by ONDRAF/NIRAS. Cementitious materials in safety cases for radioactive waste: role, evolution and interactions

International Nuclear Information System (INIS)

2012-01-01

The OECD Nuclear Energy Agency (NEA) Integration Group for the Safety Case (IGSC) organised a workshop to assess current understanding on the use of cementitious materials in radioactive waste disposal. The workshop was hosted by the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (Ondraf/Niras), in Brussels, Belgium on 17-19 November 2009. The workshop brought together a wide range of people involved in supporting safety case development and having an interest in cementitious materials: namely, cement and concrete experts, repository designers, scientists, safety assessors, disposal programme managers and regulators. The workshop was designed primarily to consider issues relevant to the post-closure safety of radioactive waste disposal, but also addressed some related operational issues, such as cementitious barrier emplacement. Where relevant, information on cementitious materials from analogous natural and anthropogenic systems was also considered. This report provides a synthesis of the workshop, and summarises its main results and findings. The structure of this report follows the workshop agenda: - Section 2 summarises plenary and working group discussions on the uses, functions and evolution of cementitious materials in geological disposal, and highlights key aspects and discussions points. - Section 3 summarises plenary and working group discussions on interactions of cementitious materials with other disposal system components, and highlights key aspects and discussions points. - Section 4 summarises the workshop session on the integration of issues related to cementitious materials using the safety case. - Section 5 presents the main conclusions from the workshop. - Section 6 contains a list of references. - Appendix A presents the workshop agenda. - Appendix B contains the abstracts and, where provided, technical papers supporting oral presentations at the workshop. - Appendix C contains the abstracts and, where provided, technical

Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning

International Nuclear Information System (INIS)

2017-02-01

The workshop was organised by the Institute for Energy Technology (IFE) on behalf of the OECD Halden Reactor Project (OECD-HRP) and in collaboration with the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA). The workshop brought together more than 100 people (operators, regulators, scientists, consultants, and contractors) from 25 countries. Program: Day 1 - Successful application of R and D in decommissioning and future needs (Welcome and Opening Speeches; Session 1: Workshop Introductory Presentations; Session 2: Experience from starting, on-going and completed decommissioning projects). Day 2 - R and D and application of advanced technologies for decommissioning (Session 3: New technologies for decommissioning; Session 4: Advanced information technologies for decommissioning). Day 3 - Improving decommissioning management on project, national and international level (Session 5: Challenges and methods for improving decommissioning; Session 6: Workshop closing)

Nuclear safety project

International Nuclear Information System (INIS)

1984-11-01

The semiannual progress report 1984/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1984 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./RW) [de

Project Nuclear Safety

International Nuclear Information System (INIS)

1981-11-01

The semiannual progress report 1981/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1981 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics, work performed, results obtained, plans for future work. This report was compiled by the project management. (orig.) [de

RESULTS FROM THE (1) DATA COLLECTION WORKSHOP, (2) MODELING WORKSHOP AND (3) DRILLING AND CORING METHODS WORKSHOP AS PART OF THE JOINT INDUSTRY PARTICIPATION (JIP) PROJECT TO CHARACTERIZE NATURAL GAS HYDRATES IN THE DEEPWATER GULF OF MEXICO

Energy Technology Data Exchange (ETDEWEB)

Stephen A. Holditch; Emrys Jones

2002-09-01

In 2000, Chevron began a project to learn how to characterize the natural gas hydrate deposits in the deepwater portions of the Gulf of Mexico. A Joint Industry Participation (JIP) group was formed in 2001, and a project partially funded by the U.S. Department of Energy (DOE) began in October 2001. The primary objective of this project is to develop technology and data to assist in the characterization of naturally occurring gas hydrates in the deepwater Gulf of Mexico. These naturally occurring gas hydrates can cause problems relating to drilling and production of oil and gas, as well as building and operating pipelines. Other objectives of this project are to better understand how natural gas hydrates can affect seafloor stability, to gather data that can be used to study climate change, and to determine how the results of this project can be used to assess if and how gas hydrates act as a trapping mechanism for shallow oil or gas reservoirs. As part of the project, three workshops were held. The first was a data collection workshop, held in Houston during March 14-15, 2002. The purpose of this workshop was to find out what data exist on gas hydrates and to begin making that data available to the JIP. The second and third workshop, on Geoscience and Reservoir Modeling, and Drilling and Coring Methods, respectively, were held simultaneously in Houston during May 9-10, 2002. The Modeling Workshop was conducted to find out what data the various engineers, scientists and geoscientists want the JIP to collect in both the field and the laboratory. The Drilling and Coring workshop was to begin making plans on how we can collect the data required by the project's principal investigators.

Report on the second uranium-series intercomparison project workshop, Harwell, 23 to 24, June 1980

International Nuclear Information System (INIS)

Ivanovich, M.; Warchal, R.M.

1981-03-01

The second Uranium-series Intercomparison Project Workshop was held on June 23 and 24, 1980 at Harwell. The aim of the Workshop was to analyse the results of Phase III of the Project and to define the future aims of the Project, if any. This report is an account of the matters raised and discussed during the two day workshop. A detailed report of a statistical analysis of USIP results - Phases I, II, and III is included. A final report submitted to USIP by CBNM, Euratom Laboratory, Geel, on the determination of the alpha activity ratio 228 Th/ 232 U in the Harwell spike solution used in USIP Phase III is reproduced in full. An account of an investigation into suitability of a limestone specimen for a geologic standard carried out at Koeln University is also given. (author)

Workshop : ACPSEM/ARPS competency based standards project

International Nuclear Information System (INIS)

Collins, L.

1996-01-01

The ACPSEM together with the Australian Radiation Protection Society has been working for nearly two years now on a competency based standards project for the professions of medical and health physicists. Competencies are being used increasingly in industry and the professions as a means of determining skill levels. For example, all the medical radiation technology streams have a CBS system in the final stages of development, and our engineering colleagues have completed theirs. Last year there was a draft document sent to all members asking for feedback. Following a vote of funding by both bodies, a project offect (Dr David Waggett) has been appointed, and has produced a very much improved set of competency standards covering all significant subspecialties in our profession. This workshop will detail the work done so far, and preview the draft document. A healthy discussion will be encouraged, as the project steering group will shortly be arranging the next steps in process. (author)

Fiscal 1999 international engineer exchange project (Coal mining technology field). Overseas workshop (Australia); 1999 nendo gijutsusha koryu jigyo (tanko gijutsu bun'ya) kokusai koryu jigyo. Kaigai workshop (Goshu)

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

This report summarizes the technology exchange with Australian coal mining engineers, the technical levels and needs on coal production, safety and environment in Australia, and the FS result on transfer of Japanese technologies, engineer exchange and joint research in a coal mining technology field. The overseas workshop (Australia) was held on Nov. 9, 1999 (Tues.) in Brisbane, Queensland. The Australia-Japan Technology Exchange Workshop on coal resources and coal mining technology includes 5 sessions (keynote address, trends and issues of coal resource development, coal resources and production technology, coal resources and safety technology, coal resources and environmental problems), and the open forum discussion on innovative technologies for coal mining. 6 Japanese specialists and 11 Australian specialists read papers. After the workshop, the participants visited Liddell Mine in New South Wales to master natural conditions, and production and safety technology levels of Australian coal mines, and to exchange various information with Australian coal mining engineers. (NEDO)

Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

International Nuclear Information System (INIS)

Hartnett, S.; Seguin, N.; Burns, M.

1995-01-01

The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned

Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

Energy Technology Data Exchange (ETDEWEB)

Hartnett, S.; Seguin, N. [Benchmark Environmental Corp., Albuquerque, NM (United States); Burns, M. [Los Alamos National Lab., NM (United States)

1995-12-31

The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned.

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

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2014-01-01

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

Effective Safety Management in Construction Project

Science.gov (United States)

Othman, I.; Shafiq, Nasir; Nuruddin, M. F.

2017-12-01

Effective safety management is one of the serious problems in the construction industry worldwide, especially in large-scale construction projects. There have been significant reductions in the number and the rate of injury over the last 20 years. Nevertheless, construction remains as one of the high risk industry. The purpose of this study is to examine safety management in the Malaysian construction industry, as well as to highlight the importance of construction safety management. The industry has contributed significantly to the economic growth of the country. However, when construction safety management is not implemented systematically, accidents will happen and this can affect the economic growth of the country. This study put the safety management in construction project as one of the important elements to project performance and success. The study emphasize on awareness and the factors that lead to the safety cases in construction project.

Spent Fuel Dissolution and Source Term Modelling in Safety Assessment. Report from a Workshop. Synthesis and extended abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-05-15

This report describes a workshop that was organised by the Swedish Nuclear Power Inspectorate (SKI) for assessment of the handling of near-field radionuclide retention processes by the Swedish Nuclear Fuel and Waste Management Company (SKB). The general objective with this type of meeting is to improve the knowledge and awareness of recent developments and to provide preliminary review comments. A number of SKB reports provided the general background for the workshop discussions. One report addresses the release of radionuclides from spent fuel, another the concentration limits related to radionuclide solubility and a third buffer radionuclide sorption and migration parameters. These reports comprise a basis for the handling of the spent fuel, solubility and sorption processes in new complete safety assessment SR-Can. The discussion and analysis of these background reports at the workshop therefore provide an essential element of preparation for the planned review of SR-Can. The review comments provided in this report are nonetheless of a preliminary character since the SR-Can report was not available at the time of the workshop and details about the incorporation of various potential safety features into the entirety of safety assessment were not known. The present report sets out the detailed objectives and format of the workshop in Section 2. Section 3 provides a high-level overview of processes that need to be taken into account. In Section 4, there is a brief discussion about the chemical and physical environment near the engineered barriers. Section 5 gives a more detailed description of spent fuel processes that affect the radionuclide releases. In Section 6, the key issues for radionuclide chemistry and the estimation of concentration limits for various radionuclides are discussed. Section 7 discusses radionuclide sorption and migration in the buffer and Section 8 presents overall conclusions from the workshop.

Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

International Nuclear Information System (INIS)

Takizawa, Masayuki; Sekimura, Naoto; Miyano, Hiroshi; Aoyama, Katsunobu

2012-01-01

Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

Report on materials characterization center workshop on stress corrosion cracking for the Salt Repository Project, December 16-17, 1986, Seattle, Washington: Workshop summary

International Nuclear Information System (INIS)

Merz, M.D.; Shannon, D.W.

1986-09-01

The Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) conducted a Workshop on Stress Corrosion Cracking for the Salt Repository Project on December 16 and 17, 1986 in Seattle, Washington. The workshop was held to formulate recommendations for addressing stress corrosion cracking (SCC) in a salt repository. It was attended by 24 representatives from major laboratories, universities, and industry. This report presents the recommendations of the workshop, along with the agenda, list of participants, questions and comments, summaries of working groups on low-strength steel and alternate materials, and materials handed out by the speakers

Workshop on the accelerator for particle therapy

International Nuclear Information System (INIS)

Inoue, M.; Ujeno, Y.

1991-02-01

A two-day workshop on the accelerator for particle therapy was held on August 22-23, 1990, with the aim of mutual understanding of medical accelerators among investigators. The state-of-the-art facilities in Japan and medical proton accelerators in Japan and other countries were introduced. This is a compilation of papers presented at the workshop: (1) particle radiotherapy at the National Institute of Radiological Sciences (NIRS); (2) proton therapy; (3) treatment planning, especially for photon and electron therapies; (4) heavy ion synchrotron project at the NIRS; (5) medical proton accelerator project of Tsukuba University and recent status of Loma Linda University Medical Center Proton Beam Facility; (6) inspection report on the Loma Linda University Medical Center Proton Beam Facility; (7) accelerator project of Kyoto University; (8) actual conditions of the 7 MeV proton linear accelerator; (9) design study of superconducting compact cyclotron prototype model; (10) medical superconducting prototype cyclotron; (11) RCNP cyclotron cascade project; (12) beam extraction from synchrotron; (13) radiation safety design in high energy particle accelerator facilities. (N.K.)

NEA/IAEA Workshop on Leadership and Management for Safety. ONR approach

International Nuclear Information System (INIS)

Harvey, Paul

2012-01-01

Paul Harvey summarised the progress made by the UK ONR on oversight of LMfS since the previous workshop in 2007. The ONR approach is based on published Safety Assessment Principles (SAPs) on Leadership and Management for Safety. The four principles cover Leadership, Capable Organisation, Decision Making and Learning. Safety culture is embodied within the LMfS SAPs/strategy rather than being treated as a specific topic. The ONR LMfS strategy draws on the lessons from major events (e.g., Texas City, Davis Besse, Columbia) and includes integration of LMfS into existing types of regulatory interventions. Key elements of the strategy include more attention to organisational and cultural factors, increased focus on Board/Director/Executive Team levels in licensees, more focus on how licensees oversee themselves, and improving ONR ability to identify precursors and influencing in combination with regulation. Guidance on Leadership and Management for safety has been produced and is undergoing trial use by ONR inspectors. The guidance is structured around the four LMfS safety assessment principles. It provides help on what to look for during interactions with licensees. ONR staff record significant points (both potential concerns and good practices) in their Intervention Reports under the 'LMfS' heading. This should enable ONR to build up a picture of strengths and weaknesses and plan interventions. Workshops on LMfS have been held for inspectors and managers. These cover organisational and cultural lessons from a range of major events and relate these to ONR LMfS strategy and draft guidance. Other interventions which form part of the strategy include 'deep slice' inspections on specific LMfS topics, and interactions with some licensee Company Boards on lessons from major events and the ONR LMfS strategy. These have been received positively by licensees. It was concluded that ongoing effort is needed to fully implement and embed the ONR LMfS strategy

CCME Climate Change Indicators -- Workshop Report

International Nuclear Information System (INIS)

2000-01-01

In an effort to give Canadians a better understanding of the climate change issue, in 1999 the Canadian Council of Ministers of the Environment (CCME) established a Project Working Group to identify and assemble a set of climate change indicators that is scientifically valid, useful and meaningful to the public. To ensure the widest possible participation of experts from all parts of the country the Project Working Group convened a two-day workshop in Toronto to take place on the 6th and 7th of November 2000. The outcome of the workshop, summarized in this report, resulted in a 'Made in Canada' framework of indicators for climate change impacts, divided into five categories: physical environment, personal health and safety, jobs and economic well-being, social and community well-being, and eco-system health. The report contains highlights of the discussions. There are seven appendices containing, respectively, a series of pre-workshop suggestions for indicators (Appendix A), the workshop agenda and backgrounder (Appendix B), a list of participants (Appendix C), presentation slides on the Canada country study (Appendix D), existing and proposed climate change indicators (Appendix E), presentation slides on communication issues (Appendix F), and notes summarizing small group discussions, including assessment of the level of interest demonstrated and opinions expressed by group members about the utility and value of each of the proposed indicators (Appendix G)

National Ignition Facility Project Site Safety Program

International Nuclear Information System (INIS)

Dun, C

2003-01-01

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

Flywheel energy storage workshop

Energy Technology Data Exchange (ETDEWEB)

O`Kain, D.; Carmack, J. [comps.

1995-12-31

Since the November 1993 Flywheel Workshop, there has been a major surge of interest in Flywheel Energy Storage. Numerous flywheel programs have been funded by the Advanced Research Projects Agency (ARPA), by the Department of Energy (DOE) through the Hybrid Vehicle Program, and by private investment. Several new prototype systems have been built and are being tested. The operational performance characteristics of flywheel energy storage are being recognized as attractive for a number of potential applications. Programs are underway to develop flywheels for cars, buses, boats, trains, satellites, and for electric utility applications such as power quality, uninterruptible power supplies, and load leveling. With the tremendous amount of flywheel activity during the last two years, this workshop should again provide an excellent opportunity for presentation of new information. This workshop is jointly sponsored by ARPA and DOE to provide a review of the status of current flywheel programs and to provide a forum for presentation of new flywheel technology. Technology areas of interest include flywheel applications, flywheel systems, design, materials, fabrication, assembly, safety & containment, ball bearings, magnetic bearings, motor/generators, power electronics, mounting systems, test procedures, and systems integration. Information from the workshop will help guide ARPA & DOE planning for future flywheel programs. This document is comprised of detailed viewgraphs.

Enhancing Safety Culture in Complex Nuclear Industry Projects

International Nuclear Information System (INIS)

Gotcheva, N.

2016-01-01

This paper presents an on-going research project “Management principles and safety culture in complex projects” (MAPS), supported by the Finnish Research Programme on Nuclear Power Plant Safety 2015-2018. The project aims at enhancing safety culture and nuclear safety by supporting high quality execution of complex projects in the nuclear industry. Safety-critical industries are facing new challenges, related to increased outsourcing and complexity in technology, work tasks and organizational structures (Milch and Laumann, 2016). In the nuclear industry, new build projects, as well as modernisation projects are temporary undertakings often carried out by networks of companies. Some companies may have little experience in the nuclear industry practices or consideration of specific national regulatory requirements. In large multinational subcontractor networks, the challenge for assuring nuclear safety arises partly from the need to ensure that safety and quality requirements are adequately understood and fulfilled by each partner. Deficient project management practices and unsatisfactory nuclear safety culture in project networks have been recognised as contributing factors to these challenges (INPO, 2010). Prior evidence indicated that many recent major projects have experienced schedule, quality and financial challenges both in the nuclear industry (STUK, 2011) and in the non-nuclear domain (Ahola et al., 2014; Brady and Davies, 2010). Since project delays and quality issues have been perceived mainly as economic problems, project management issues remain largely understudied in safety research. However, safety cannot be separated from other performance aspects if a systemic view is applied. Schedule and quality challenges may reflect deficiencies in coordination, knowledge and competence, distribution of roles and responsibilities or attitudes among the project participants. It is increasingly understood that the performance of the project network in all

3. Halden Reactor Project Workshop

International Nuclear Information System (INIS)

Louka, Michael N.

2005-09-01

A workshop was held in Halden 2nd-3rd March 2005 to discuss 'VR in the Future Industrial Workplace: Working Together - Regardless of Distance'. The workshop sessions and discussions focused on design, operations and maintenance, training, and engineering virtual reality systems, and provided useful insights into the current state of the art of research and development in the fields of virtual and augmented reality. (Author)

Nuclear Safety Project

International Nuclear Information System (INIS)

1978-11-01

The 13th semi-annual report 1/78 is a description of work within the Nuclear Safety Project performed in the first six months of 1978 in the nuclear safety field by KFK institutes and departments and by external institutions on behalf of KfK. It includes for each individual research activity short summaries on - work completed, - essential results, - plans for the near future. (orig./RW) [de

Workshop presentations

International Nuclear Information System (INIS)

Sanden, Per-Olof; Edland, Anne; Reiersen, Craig; Mullins, Peter; Ingemarsson, Karl-Fredrik; Bouchard, Andre; Watts, Germaine; Johnstone, John; Hollnagel, Erik; Ramberg, Patric; Reiman, Teemu

2009-01-01

An important part of the workshop was a series of invited presentations. The presentations were intended to both provide the participants with an understanding of various organisational approaches and activities as well as to stimulate the exchange of ideas during the small group discussion sessions. The presentation subjects ranged from current organisational regulations and licensee activities to new organisational research and the benefits of viewing organisations from a different perspective. There were more than a dozen invited presentations. The initial set of presentations gave the participants an overview of the background, structure, and aims of the workshop. This included a short presentation on the results from the regulatory responses to the pre-workshop survey. Representatives from four countries (Sweden, Canada, Finland, and the United Kingdom) expanded upon their survey responses with detailed presentations on both regulatory and licensee safety-related organisational activities in their countries. There were also presentations on new research concerning how to evaluate safety critical organisations and on a resilience engineering perspective to safety critical organisations. Below is the list of the presentations, the slides of which being available in Appendix 2: 1 - Workshop Welcome (Per-Olof Sanden); 2 - CSNI Working Group on Human and Organisational Factors (Craig Reiersen); 3 - Regulatory expectations on justification of suitability of licensee organisational structures, resources and competencies (Anne Edland); 4 - Justifying the suitability of licensee organisational structures, resources and competencies (Karl-Fredrik Ingemarsson); 5 - Nuclear Organisational Suitability in Canada (Andre Bouchard); 6 - Designing and Resourcing for Safety and Effectiveness (Germaine Watts); 7 - Organisational Suitability - What do you need and how do you know that you've got it? (Craig Reiersen); 8 - Suitability of Organisations - UK Regulator's View (Peter

The Halden Reactor Project workshop meeting on human centred automation and function allocation methods

International Nuclear Information System (INIS)

Sebok, Angelia; Green, Marit; Larsen, Marit; Miberg, Ann Britt; Morisseau, Dolores

1998-02-01

A workshop on Human Centred Automation (HCA) and Function Allocation Methods was organised in Halden, September 29-30, 1997. The purpose of the workshop was to discuss and make recommendations on requirements for the Halden Project research agenda. The workshop meeting began with several presentations summarising current issues in HCA, Function Allocation Methods and Functional Modelling. Invited speakers presented their research or modelling efforts. Following the presentations, the workshop was divided into three working groups, all tasked with answering the same four questions: (1) What are the most important issues in Human Centred Automation? (2) Which strengths could be achieved by integrating Functional Modelling Methods into experimental Human Centred Automation research? (3) How should analytical and experimental methods be balanced? (4) What are the most important aspects in automation design methodology? Each group discussed the questions and produced specific recommendations that were summarised by the group's facilitator in a joint session of the workshop. (author)

Nuclear Safety Project

International Nuclear Information System (INIS)

1983-12-01

The semiannual progress report 1983/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1983 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics work performed, results obtained and plans for future work. (orig./RW) [de

Nuclear safety project

International Nuclear Information System (INIS)

Anon.

1980-11-01

The 17th semi-annual report 1980/1 is a description of work within the Nuclear Safety Project performed in the first six months of 1980 in the nuclear safety field by KfK institutes and departments and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics - work performed, results obtained, plans for future work. (orig.) [de

INDICO Workshop

CERN Multimedia

CERN. Geneva; Fabbrichesi, Marco

2004-01-01

The INtegrated DIgital COnferencing EU project has finished building a complete software solution to facilitate the MANAGEMENT OF CONFERENCES, workshops, schools or simple meetings from their announcement to their archival. Everybody involved in the organization of events is welcome to join this workshop, in order to understand the scope of the project and to see demonstrations of the various features.

Workshop on Radiological characterisation for decommissioning - Compilation of abstracts, papers, presentations and posters

International Nuclear Information System (INIS)

2012-01-01

The OECD Nuclear Energy Agency (NEA), in cooperation with Studsvik Nuclear AB, the Swedish Radiation Safety Authority (SSM), Swedish Nuclear Fuel and Waste Management Co (SKB) and AB SVAFO, has arranged a workshop on Radiological characterisation for decommissioning and dismantling. The objective of the workshop was to highlight, examine and discuss strategic issues related to radiological characterisation of nuclear facilities to facilitate their safe and efficient decommissioning. The workshop was a forum for learning about current practices, exchange of experiences of both successful and less successful projects, discussion of best practice and needs for improvement, and development of networks in the area of radiological characterisation, waste management and decommissioning. The workshop was arranged in coordination with an ongoing NEA WPDD project on radiological characterisation for decommissioning. The outcome of the workshop was captured in workshop proceedings and in the final NEA WPDD project report. A three-day programme was planned. A short introduction by representatives from Studsvik and OECD/NEA started the workshop followed by presentations by invited speakers from international organisations. Four topical sessions covered issues relating to Characterisation of materials and systems, Characterisation of rooms and buildings, Characterisation of land and groundwater, Software support, record keeping, quality assurance and logistics. Each session contained 3 - 5 presentations and group discussions. Each session was concluded with a short analysis of the presentations and the outcome of the group discussions. The workshop also held a poster session with topics as above. After the formal closing of the workshop, half a day was dedicated for guided tours at the Studsvik and SVAFO facilities. It was possible to visit waste management facilities, the reactor decommissioning project and materials technology laboratories. This document is the Compilation of

A Project-Based Engineering and Leadership Workshop for High School Students

Science.gov (United States)

Ryder, Linda Sue; Pegg, Jerine; Wood, Nathan

2012-01-01

Summer outreach programs provide pre-college participants an introduction to college life and exposure to engineering in an effort to raise the level of interest and bring more students into engineering fields. The Junior Engineering, Mathematics, and Science (JEMS) program is a project-based summer workshop in which teams of high school students…

Mont Terri Project - Proceedings of the 10 Year Anniversary Workshop

International Nuclear Information System (INIS)

Hugi, M.; Bossart, P.; Hayoz, P.

2007-01-01

This book is a compilation of 12 reports presented at the St-Ursanne workshop. The workshop was dedicated to the scientific community of the Mont Terri partner organisations, their management and scientific/technical staff, involved research organisations and key contractors. The purpose of the event was to acknowledge the excellent research work that has been performed over the last decade, to evaluate and discuss the present state of knowledge in selected research areas and to explore the potential for future research activities. The topical areas addressed in the workshop are of particular importance with regard to deep geological disposal of radioactive waste and focused on the issues of coupled phenomena and transport processes in argillaceous rock and the demonstration (in underground rock laboratories) of disposal feasibility. After showing the history of the Mont Terri project and the general geology of Northwestern Switzerland, the different presentations are distributed into 3 topics: (a) Coupled phenomena in argillaceous rock, (b) Transport processes in argillaceous rock, and (c) Demonstration of disposal feasibility in underground rock laboratories. The last chapter describes the research still needed and the Mont Terri rock laboratory

Intermodal safety research needs report of the sixth workshop on national transportation problems

Energy Technology Data Exchange (ETDEWEB)

Warshawer, A.J. (ed.)

1976-04-01

This conference brought together DOT policymakers, university principal investigators and other professionals to consider the intermodal safety research requirements of the Department of Transportation. The objectives of the conference were: (1) to highlight safety problems and needed transportation safety research identified by DOT modal safety managers and to stimulate university or university/industry teams to respond with research proposals which emphasize multi-modal applicability and a system view; and (2) to provide a forum for university research groups to inform DOT safety managers of promising new directions in transportation safety research and new tools with which to address safety related problems. The conference addressed the research requirements for safety as identified by the Statement of National Transportation Policy and by the modal safety managers in three principal contexts, each a workshop panel: I, Inter-Institutional Problems of Transportation Safety. Problems were described as: Federal-State, local; Federal-Industry; Federal-Public, Consumer groups. II, Goal Setting and Planning for Transportation Safety Programs. Issues were: modifying risk behavior, safety as a social value, and involving citizens in development of standards as a way of increasing probability of achieving program objectives. III, DOT Information, Management, and Evaluation Systems Requirements. Needs were: data requirements and analytic tools for management of safety programs.

The "Chemistry Is in the News" Project: Can a Workshop Induce a Pedagogical Change?

Science.gov (United States)

Barak, Miri; Carson, Kathleen M.; Zoller, Uri

2007-01-01

Chemistry Is in the News (CIITN) is an innovative project aimed at enhancing higher-order cognitive skills (HOCS) via connecting university-level chemistry to everyday life and real-world issues. The CIITN project and its related Web tools were presented in a workshop to illustrate their conceptual framework, educational potential, and…

Engineered barrier systems (EBS) in the context of the entire safety case

International Nuclear Information System (INIS)

2003-01-01

A joint NEA-EC workshop entitled 'Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case' was organised in Oxford on 25-27 September 2002 and hosted by United Kingdom Nirex Limited. The main objectives of the workshop were to provide a status report on engineered barrier systems in various national radioactive waste management programmes considering deep geological disposal; to establish the value to member countries of a project on EBS; and to define such a project's scope, timetable and modus operandi. This report presents the outcomes of this workshop. (author)

Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case

International Nuclear Information System (INIS)

2005-01-01

A joint NEA-EC workshop entitled ''Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case'' was organised in Oxford on 25-27 September 2002 and hosted by United Kingdom Nirex Limited. The main objectives of the workshop were to provide a status report on engineered barrier systems in various national radioactive waste management programmes considering deep geological disposal; to establish the value to member countries of a project on EBS; and to define such a project scope, timetable and modus operandi. This report presents the outcomes of this workshop. (author)

Use of OECD/NEA Data Project Products in Probabilistic Safety Assessment

International Nuclear Information System (INIS)

Cherkas, G.; Raducu, Gheorghe; Riznic, J.; Yalaoui, S.; Huang, Hui-Wen; Holy, Jaroslav; Holmberg, Jan-Erik; Sandberg, Jorma; Balmain, Michel; Bonnevialle, Anne-Marie; Curnier, Florence; Georgescu, Gabriel; Lanore, Jeanne-Marie; Lindner, Arndt; Fujimoto, Haruo; Ahn, Kwang-Il; Hwang, Taesuk; Jang, Seung-Cheol; Husarcek, Jan; Kovacs, Zoltan; Vazquez, Teresa; Johanson, Gunnar; Liwaang, Bo; Nyman, Ralph; Dang, Vinh; Schoen, Gerhard; Brook, Kevin; Hamblen, David; Siu, Nathan; Sturzebecher, Karl; Tobin, Margaret; Wood, Jeff; Amri, Abdallah; Breest, Axel

2014-01-01

The Nuclear Energy Agency (NEA)/Committee for the Safety of Nuclear Installations' (CSNI) Working Group on Risk Assessment (WGRISK) is tasked with supporting the improved use of Probabilistic Safety Assessment (PSA) in risk informed regulation and safety management through the analysis of results and the development of perspectives regarding potentially important risk contributors and associated risk reduction strategies. The task consists of the following major activities: Development, distribution, and completion of survey questionnaires; Analysis of survey questionnaire results at a task workshop; Preparation of the final task report. The main objectives of this task, as proposed by WGRISK and approved by CSNI, are the following: - Identification and characterization of the current uses of OECD data project products and data in support of PSA. In this context, the term 'products' refers to data analysis results, technical reports, and other project outputs. - Identification and characterization of technical and programmatic characteristics that either support or impede use of data project products in PSA. This includes an assessment of which PSA parameters could be potentially estimated from the various data project products and gaps between available product information and PSA data needs. - Identification of recommendations for enhancing the usefulness of data project products and the coordination between WGRISK and the data projects. This task report consists of the following sections: - Chapter 1 Provides a general overview of motivation and approach used for this task. - Chapter 2 Describes scope and objectives of the task. - Chapter 3 Provides an overview of the ICDE, FIRE, OPDE/CODAP, and COMPSIS data projects. For each project, the project objectives, project history, data collection methodology and quality assurance, project status, example PSA Applications, and information related to project participation is provided. - Chapter 4 Describes the

New innovative educational method to prevent accidents involving young road users (aged 15-24 – European Road Safety Tunes

Directory of Open Access Journals (Sweden)

Jankowska-Karpa Dagmara

2017-01-01

Full Text Available The article presents a new teaching method designed to improve road safety among young road users. Developed under “European Road Safety Tunes”, this international project was cofunded by EU DG MOVE. Its main aim is to improve road safety and minimize the number of road accidents, injuries and fatalities among road users who are 15-24 years old. The Safety Tunes method contains a series of workshops addressed to young vocational school students: cyclists, moped and motor riders and car drivers. The workshops incorporate peer and emotive education, and delivery of road safety related messages through different types of artistic forms. The topics tackled during class address awareness of possible risks and risk-behaviour, prevention of distraction and reduction in young fatalities and serious injuries on the road. All actions within the project are evaluated, both in terms of the impact of the workshops on students’ attitudes towards road safety problems and in terms of process assessment.

Proceedings of the NOAMI workshop : a workshop to explore perspectives on risk assessment for orphaned and abandoned mines

International Nuclear Information System (INIS)

2009-03-01

This workshop hosted by the National Orphaned/Abandoned Mines Initiative (NOAMI) discussed risk assessment strategies and perspectives for orphaned and abandoned mines in Canada. Different perspectives related to the risk assessment process were considered by participants from local, provincial, federal, and territorial agencies as well as non-governmental, academic, and mining industry organizations. Strategies for effectively communicating with local communities were discussed. New methods of assessing risk related to bioavailability and bioaccessibility were reviewed along with approaches to risk assessment and risk management in relation to the Environmental Management Act. Case studies of risk assessment and remediation projects were presented. The workshop presentations were divided into the following 6 sessions: (1) keynote, (2) opening panel, (3) human health panel, (4) ecological panel, (5) geotechnical-safety risk assessment panel, and (6) case studies and perspectives. The workshop featured 22 presentations, of which 2 have been catalogued separately for inclusion in this database. A report on detailed ecological risk assessment (DERA) in British Columbia prepared by the Science Advisory Board for Contaminated Sites in British Columbia (BC) was included, as well as a final report that summarized presentations given at the workshop. refs., tabs., figs

Project safety studies - nuclear waste management (PSE)

International Nuclear Information System (INIS)

1981-10-01

The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

CNA Maritime Asia Project. Workshop One: The Yellow and East China Seas

Science.gov (United States)

2012-05-01

in 2011.8 In October, South Korean Coast Guard forces used tear gas and rubber bullets to subdue Chinese fishermen wielding clubs and shovels.9 An...tation Disputes in the East China Sea,” NBR Special Report No.35 (December 2011): 135 and 141. 39 CNA Maritime Asia Project Workshop One: The Yellow

Proceedings of the 2010 Canadian Dam Association's public safety around dams workshop

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

Nearly 30 people have drowned in dam-related incidents over the last 10 years in Canada. The Canadian public is now calling for improved safety guidelines. Public interaction with dams is increasing as a result of interest in extreme sports and perceived rights of access. However, many members of the public are not aware of the dangers posed by dams. This workshop provided a forum to discuss proposals for a draft publication of the Canadian Dam Association (CDA) guidelines for public safety and security around dams. Issues related to current legislation and liability were discussed. Methods of increasing public awareness of the hazards posed by dams included increased signage in dam locations, the use of audible and visual alert systems, and the use of booms and buoys. The responsibilities of dam owners in ensuring the safety of dams were also discussed. The conference featured 5 presentations, of which 2 have been catalogued separately for inclusion in this database. tabs., figs.

A review of planetary and space science projects presented at iCubeSat, the Interplanetary CubeSat Workshop

Science.gov (United States)

Johnson, Michael

2015-04-01

iCubeSat, the Interplanetary CubeSat Workshop, is an annual technical workshop for researchers working on an exciting new standardised platform and opportunity for planetary and space scientists. The first workshop was held in 2012 at MIT, 2013 at Cornell, 2014 at Caltech with the 2015 workshop scheduled to take place on the 26-27th May 2015 at Imperial College London. Mission concepts and flight projects presented since 2012 have included orbiters and landers targeting asteroids, the moon, Mars, Venus, Saturn and their satellites to perform science traditionally reserved for flagship missions at a fraction of their cost. Some of the first missions proposed are currently being readied for flight in Europe, taking advantage of multiple ride share launch opportunities and technology providers. A review of these and other interplanetary CubeSat projects will be presented, covering details of their science objectives, instrument capabilities, technology, team composition, budget, funding sources, and the other programattic elements required to implement this potentially revolutionary new class of mission.

76 FR 81929 - South Carolina Public Service Authority; Notice of Workshop for Santee Cooper Hydroelectric Project

Science.gov (United States)

2011-12-29

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 199-205] South Carolina Public Service Authority; Notice of Workshop for Santee Cooper Hydroelectric Project On May 26 and...) and the South Carolina Public Service Authority (SCPSA), licensee for the Santee-Cooper Hydroelectric...

Computational Fluid Dynamics (CFD) in Nuclear Reactor Safety (NRS) - Proceedings of the workshop on Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS)

International Nuclear Information System (INIS)

2008-01-01

Computational Fluid Dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coolant system to be better described. The Committee on the Safety of Nuclear Installations (CSNI), which is responsible for the activities of the OECD Nuclear Energy Agency that support advancing the technical base of the safety of nuclear installations, has in recent years conducted an important activity in the CFD area. This activity has been carried out within the scope of the CSNI working group on the analysis and management of accidents (GAMA), and has mainly focused on the formulation of user guidelines and on the assessment and verification of CFD codes. It is in this GAMA framework that a first workshop CFD4NRS was organized and held in Garching, Germany in 2006. Following the CFD4NRS workshop, this XCFD4NRS Workshop was intended to extend the forum created for numerical analysts and experimentalists to exchange information in the field of Nuclear Reactor Safety (NRS) related activities relevant to Computational Fluid Dynamics (CFD) validation, but this time with more emphasis placed on new experimental techniques and two-phase CFD applications. The purpose of the workshop was to provide a forum for numerical analysts and experimentalists to exchange information in the field of NRS-related activities relevant to CFD validation, with the objective of providing input to GAMA CFD experts to create a practical, state-of-the-art, web-based assessment matrix on the use of CFD for NRS applications. The scope of XCFD4NRS includes: - Single-phase and two-phase CFD simulations with an emphasis on validation in areas such as: boiling flows, free-surface flows, direct contact condensation and turbulent mixing. These applications should relate to NRS-relevant issues such as: pressurized thermal shocks, critical heat flux, pool heat exchangers, boron dilution, hydrogen

ELECTRICAL SAFETY IMPROVEMENT PROJECT A COMPLEX WIDE TEAMING INITIATIVE

Energy Technology Data Exchange (ETDEWEB)

GRAY BJ

2007-11-26

This paper describes the results of a year-long project, sponsored by the Energy Facility Contractors Group (EFCOG) and designed to improve overall electrical safety performance throughout Department of Energy (DOE)-owned sites and laboratories. As evidenced by focused metrics, the Project was successful primarily due to the joint commitment of contractor and DOE electrical safety experts, as well as significant support from DOE and contractor senior management. The effort was managed by an assigned project manager, using classical project-management principles that included execution of key deliverables and regular status reports to the Project sponsor. At the conclusion of the Project, the DOE not only realized measurable improvement in the safety of their workers, but also had access to valuable resources that will enable them to do the following: evaluate and improve electrical safety programs; analyze and trend electrical safety events; increase electrical safety awareness for both electrical and non-electrical workers; and participate in ongoing processes dedicated to continued improvement.

Proceedings of the DOE/Yucca Mountain Site Characterization Project Radionuclde Adsorption Workshop at Los Alamos National Laboratory, September 11--12, 1990

International Nuclear Information System (INIS)

Canepa, J.A.

1992-08-01

Los Alamos National Laboratory hosted a workshop on radionuclide adsorption for the Department of Energy (DOE)/Yucca Mountain Site Characterization Project on September 11 and 12, 1990. The purpose of the workshop was to respond to a recommendation by the Nuclear Waste Technical Review Board that the DOE organize a radionuclide adsorption workshop to be attended by the DOE and its contractors involved in the measurement and modeling of such adsorption. The workshop would have two general purposes: (a) to determine the applicability of available radionuclide adsorption data on tuff and models for predicting such adsorption under existing and postclosure conditions at Yucca Mountain and (b) to establish what additional radionuclide adsorption research and model development are needed. Individual projects are processed separately for the databases

Impact of Construction Health & Safety Regulations on Project ...

African Journals Online (AJOL)

Impact of Construction Health & Safety Regulations on Project Parameters in Nigeria: Consultants and Contractors View. ... The study recommends that better attention is given to health and safety should as a project parameter and that related practice notes and guidelines should be evolved for all project stakeholders.

Accelerating the Development of 21st-Century Toxicology: Outcome of a Human Toxicology Project Consortium Workshop

Science.gov (United States)

Stephens, Martin L.; Barrow, Craig; Andersen, Melvin E.; Boekelheide, Kim; Carmichael, Paul L.; Holsapple, Michael P.; Lafranconi, Mark

2012-01-01

The U.S. National Research Council (NRC) report on “Toxicity Testing in the 21st century” calls for a fundamental shift in the way that chemicals are tested for human health effects and evaluated in risk assessments. The new approach would move toward in vitro methods, typically using human cells in a high-throughput context. The in vitro methods would be designed to detect significant perturbations to “toxicity pathways,” i.e., key biological pathways that, when sufficiently perturbed, lead to adverse health outcomes. To explore progress on the report’s implementation, the Human Toxicology Project Consortium hosted a workshop on 9–10 November 2010 in Washington, DC. The Consortium is a coalition of several corporations, a research institute, and a non-governmental organization dedicated to accelerating the implementation of 21st-century Toxicology as aligned with the NRC vision. The goal of the workshop was to identify practical and scientific ways to accelerate implementation of the NRC vision. The workshop format consisted of plenary presentations, breakout group discussions, and concluding commentaries. The program faculty was drawn from industry, academia, government, and public interest organizations. Most presentations summarized ongoing efforts to modernize toxicology testing and approaches, each with some overlap with the NRC vision. In light of these efforts, the workshop identified recommendations for accelerating implementation of the NRC vision, including greater strategic coordination and planning across projects (facilitated by a steering group), the development of projects that test the proof of concept for implementation of the NRC vision, and greater outreach and communication across stakeholder communities. PMID:21948868

In-depth Analysis of Pattern of Occupational Injuries and Utilization of Safety Measures among Workers of Railway Wagon Repair Workshop in Jhansi (U.P.).

Science.gov (United States)

Gupta, Shubhanshu; Malhotra, Anil K; Verma, Santosh K; Yadav, Rashmi

2017-01-01

Occupational injuries constitute a global health challenge, yet they receive comparatively modest scientific attention. Pattern of occupational injuries and its safety precautions among wagon repair workers is an important health issue, especially in developing countries like India. To assess the pattern of occupational injuries and utilization of safety measures among railway wagon repair workshop workers in Jhansi (U.P.). Railway wagon repair workshop urban area, Jhansi (U.P). Occupation-based cross-sectional study. A cross-sectional study was conducted among 309 workers of railway workshop in Jhansi (U.P.) who were all injured during the study period of 1 year from July 2015 to June 2016. Baseline characteristics, pattern of occupational injuries, safety measures, and their availability to and utilization by the participants were assessed using a pretested structured questionnaire. Data obtained were collected and analyzed statistically by simple proportions and Chi-square test. The majority of studied workers aged between 38 and 47 years ( n = 93, 30.6%) followed by 28-37 years ( n = 79, 26%). Among the pattern of occupational injuries, laceration (28.7%) was most common followed by abrasion/scratch (21%). Safety shoes and hat were utilized 100% by all workers. Many of them had more than 5 years of experience ( n = 237, 78%). Age group, education level, and utilization of safety measures were significantly associated with pattern of occupational injuries in univariate analysis ( P safety measures is low among workers on railway wagon repair workshop, which highlights the importance of strengthening safety regulatory services toward this group of workers. Younger age group workers show a significant association with open wounds and surface wounds. As the education level of workers increases, the incidence of injuries decreases. Apart from shoes, hat, and gloves, regular utilization of other personal protective equipment was not seen.

PV radiometrics workshop proceedings

Energy Technology Data Exchange (ETDEWEB)

Myers, D.R.

1995-09-01

This report documents presentations and discussions held at the Photovoltaics Radiometeric Measurements Workshop conducted at Vail, Colorado, on July 24 and 25, 1995. The workshop was sponsored and financed by the Photovoltaic Module and Systems Performance and Engineering Project managed by Richard DeBlasio, Principal Investigator. That project is a component of the National Renewable Energy Laboratory (NREL) Photovoltaic Research and Development Program, conducted by NREL for the US Department of Energy, through the NREL Photovoltaic Engineering and Applications Branch, managed by Roland Hulstrom. Separate abstracts have been prepared for articles from this workshop.

Nuclear Safety Project. Annual report 1983

International Nuclear Information System (INIS)

1984-06-01

The annual report 1983 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1983 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig.) [de

Nuclear safety project. Annual report 1985

International Nuclear Information System (INIS)

1986-07-01

The annual report 1985 is a detailed description (in German language) of work within the nuclear safety project performed in 1985 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work performed, results obtained and plans for future work. This report was compiled by the project management. (orig./HP) [de

Cesium legacy safety project management work plan

International Nuclear Information System (INIS)

Durham, J.S.

1998-01-01

This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)

Indonesian students' participation in an interprofessional learning workshop.

Science.gov (United States)

Ernawati, Desak Ketut; Lee, Ya Ping; Hughes, Jeffery

2015-01-01

Interprofessional learning activities, such as workshops allow students to learn from, with and about each other. This study assessed the impact on Indonesian health students' attitudes towards interprofessional education (IPE) from participating in a workshop on medication safety. The students attended a two-day IPE workshop on medication safety. Thirty-five (48.6%) students completed pre-/post-workshop surveys using a modified Readiness for Interprofessional Learning Scale (RIPLS) survey. The post-workshop survey also had a series of open-ended questions. Students' responses to each RIPLS statement pre-/post-workshop were compared, whilst their responses to open-ended questions in post-workshop survey were thematically analysed. Students reported positive attitudinal changes on statements of shared learning and teamwork sub-scale (Wilcoxon p value importance of teamwork and communication skills. This study found that learning with other health students through an IPE workshop improved medical, nursing and pharmacy students' attitudes towards the importance of shared learning, teamwork and communication in healthcare service.

NASA's Aviation Safety and Modeling Project

Science.gov (United States)

Chidester, Thomas R.; Statler, Irving C.

2006-01-01

The Aviation Safety Monitoring and Modeling (ASMM) Project of NASA's Aviation Safety program is cultivating sources of data and developing automated computer hardware and software to facilitate efficient, comprehensive, and accurate analyses of the data collected from large, heterogeneous databases throughout the national aviation system. The ASMM addresses the need to provide means for increasing safety by enabling the identification and correcting of predisposing conditions that could lead to accidents or to incidents that pose aviation risks. A major component of the ASMM Project is the Aviation Performance Measuring System (APMS), which is developing the next generation of software tools for analyzing and interpreting flight data.

Report of the COG/IAEA international workshop on managing nuclear safety at CANDU (PHWR) plants. Working material

International Nuclear Information System (INIS)

1997-01-01

The workshop, hosted by COG and co-sponsored by the International Atomic Energy Agency (IAEA, Vienna) was held in Toronto, April 28 - May 1st, 1997. The 40 participants included senior managers from IAEA member countries operating or constructing CANDU (PHWR) stations. All the offshore utilities with PHWR stations in Korea, Romania, India, Argentina, Pakistan, and China were present with their domestic counterparts from Ontario Hydro Nuclear, Hydro Quebec, New Brunswick Power, and AECL. The objectives of the workshop were to: provide a forum for exchange of ideas among nuclear safety managers operating CANDU (PHWR) stations and to learn from each other's experiences; to foster sharing of information on different operating approaches to managing safety and, in particular, to highlight the strategies for controlling the overall plant risk to a low level; to identify and discuss issues of mutual interest pertinent to PHWR stations and to define future follow-up activities. Refs, figs

Report of the COG/IAEA international workshop on managing nuclear safety at CANDU (PHWR) plants. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

The workshop, hosted by COG and co-sponsored by the International Atomic Energy Agency (IAEA, Vienna) was held in Toronto, April 28 - May 1st, 1997. The 40 participants included senior managers from IAEA member countries operating or constructing CANDU (PHWR) stations. All the offshore utilities with PHWR stations in Korea, Romania, India, Argentina, Pakistan, and China were present with their domestic counterparts from Ontario Hydro Nuclear, Hydro Quebec, New Brunswick Power, and AECL. The objectives of the workshop were to: provide a forum for exchange of ideas among nuclear safety managers operating CANDU (PHWR) stations and to learn from each other`s experiences; to foster sharing of information on different operating approaches to managing safety and, in particular, to highlight the strategies for controlling the overall plant risk to a low level; to identify and discuss issues of mutual interest pertinent to PHWR stations and to define future follow-up activities. Refs, figs.

Use of safety management practices for improving project performance.

Science.gov (United States)

Cheng, Eddie W L; Kelly, Stephen; Ryan, Neal

2015-01-01

Although site safety has long been a key research topic in the construction field, there is a lack of literature studying safety management practices (SMPs). The current research, therefore, aims to test the effect of SMPs on project performance. An empirical study was conducted in Hong Kong and the data collected were analysed with multiple regression analysis. Results suggest that 3 of the 15 SMPs, which were 'safety committee at project/site level', 'written safety policy', and 'safety training scheme' explained the variance in project performance significantly. Discussion about the impact of these three SMPs on construction was provided. Assuring safe construction should be an integral part of a construction project plan.

Knowledge management in Nordic NPPs. Summary report of the findings from the workshop

Energy Technology Data Exchange (ETDEWEB)

Nilsen, S. [Inst. for Energy Technology, Halden (Norway)

2005-04-01

The title of the reported project is 'Nordic Nuclear Safety Research (NKS) Workshop on Knowledge Management in Nordic NPPs'. One important objective of this workshop was to explore if and how knowledge retention activities could be coordinated between the various Nordic utilities. The main conclusions of the workshop can be summed up as follows: Establishing good knowledge management routines is recognized by many utilities today. However, there seem to be no real consensus on what should be focused on in the present situation. Maybe the most pressing problem is to avoid undesirable consequences of the massive retirement soon to follow. Still, there is no consensus on what those consequences might be, and what should be done to avoid them. (au)

Knowledge management in Nordic NPPs. Summary report of the findings from the workshop

International Nuclear Information System (INIS)

Nilsen, S.

2005-04-01

The title of the reported project is 'Nordic Nuclear Safety Research (NKS) Workshop on Knowledge Management in Nordic NPPs'. One important objective of this workshop was to explore if and how knowledge retention activities could be coordinated between the various Nordic utilities. The main conclusions of the workshop can be summed up as follows: Establishing good knowledge management routines is recognized by many utilities today. However, there seem to be no real consensus on what should be focused on in the present situation. Maybe the most pressing problem is to avoid undesirable consequences of the massive retirement soon to follow. Still, there is no consensus on what those consequences might be, and what should be done to avoid them. (au)

Proceedings of the CSNI/IAEA workshop on maintaining oversight of licensee safety culture - methods and approaches. Held from 21 to 23 May 2007 in Chester, UK

International Nuclear Information System (INIS)

2008-01-01

Weaknesses in safety culture have contributed to a number of high profile events in the nuclear and other high hazard sectors. The nuclear industry also faces challenges such as deregulation, out-sourcing, phase-out, upgrading and new builds which, if not properly planned and implemented, have the potential to make a negative impact on safety culture. These factors have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. An NEA/CSNI/IAEA workshop was therefore held in Chester, UK, in May 2007 in order to explore and discuss the approaches that different regulatory bodies are taking to maintain oversight of licensee safety culture. It was organised by the UK Nuclear Installations Inspectorate on behalf of the CSNI's Working Group on Human and Organisational Factors. This report sets out the findings of the Chester workshop. The workshop was attended by 50 representatives of nuclear regulatory bodies in 20 countries plus IAEA, WANO, EU and NEA. It included both specialists in safety culture and site/resident inspectors, whose attendance was facilitated by the CNRA's Working Group on Inspection Practices. The workshop comprised structured discussion sessions, in which a set of issues were explored by small discussion groups and then discussed in plenary, complemented by short presentations on national regulatory positions. The workshop revealed a broad consensus that nuclear regulators should have processes in place to maintain oversight of licensee safety culture. The approaches

First Ph.D. Student Workshop of the Hermann von Helmholtz Association of National Research Centers (HGF) on ''Nuclear Safety Research''

International Nuclear Information System (INIS)

Knebel, J.U.; Sanchez Espinoza, V.H.

2006-03-01

The First Ph.D. Student Workshop ''Nuclear Safety Research'' of the Helmholtz Association of National Research Centers (HGF)'' was jointly organized by the Research Center Karlsruhe GmbH and the Energie Baden-Wuerttemberg AG (EnBW) from Wednesday 9th to Friday 11th March 2005. The workshop was opened with welcome greetings by Dr. Peter Fritz, Forschungszentrum Karlsruhe. Subsequently Dr. Joachim U. Knebel explained the main goals and the content of the workshop. The young scientists reported in 28 high-level presentations about their research work which covered a wide spectrum from reactor safety, partitions and transmutation, and innovative reactor systems, to safety research for nuclear waste disposal. The junior researchs showed excellent professional competence and demonstrated presentation qualities at the highest level. The successful funding of two Virtual Institutes, namely: the ''Competence in Nuclear Technologies'' and ''Functional Characteristics of Aquatic Interfaces both co-ordinated by Forschungszentrum Karlsruhe'', by the President of the Helmholtz Association Prof. Walter Kroell was the motivation for the organization of this first Ph.D. Student Workshop. Thanks to these two Virtual Institutes, the Reseach Center Karlsruhe and Juelich together with several univer-sities i.e. RWTH Aachen, Heidelberg, Karlsruhe, Muenster, and Stuttgart, have successfully financed eight Ph.D. and two post-doctoral students. Moreover, young scientists of the European Institute for Transuranium Elements (ITU) and additional seven Ph.D. Students, who are sponsored by the German nuclear industry (Framatome ANP, RWE Power, EnBW) in the frame of the Alliance Competence in on Nuclear Technology, and who are trained at Forschungszentrum Karlsruhe, actively contributed to this workshop. The EnBW-Award was handed over by Dr. Hans-Josef Zimmer, member of the board of directors of the EnBW-Kraftwerksgesellschaft, to Mrs. Ayelet Walter from the University of Stuttgart for the best

Nuclear thermal rocket workshop reference system Rover/NERVA

International Nuclear Information System (INIS)

Borowski, S.K.

1991-01-01

The Rover/NERVA engine system is to be used as a reference, against which each of the other concepts presented in the workshop will be compared. The following topics are reviewed: the operational characteristics of the nuclear thermal rocket (NTR); the accomplishments of the Rover/NERVA programs; and performance characteristics of the NERVA-type systems for both Mars and lunar mission applications. Also, the issues of ground testing, NTR safety, NASA's nuclear propulsion project plans, and NTR development cost estimates are briefly discussed

Risk Management Techniques and Practice Workshop Workshop Report

Energy Technology Data Exchange (ETDEWEB)

Quinn, T; Zosel, M

2008-12-02

At the request of the Department of Energy (DOE) Office of Science (SC), Lawrence Livermore National Laboratory (LLNL) hosted a two-day Risk Management Techniques and Practice (RMTAP) workshop held September 18-19 at the Hotel Nikko in San Francisco. The purpose of the workshop, which was sponsored by the SC/Advanced Scientific Computing Research (ASCR) program and the National Nuclear Security Administration (NNSA)/Advanced Simulation and Computing (ASC) program, was to assess current and emerging techniques, practices, and lessons learned for effectively identifying, understanding, managing, and mitigating the risks associated with acquiring leading-edge computing systems at high-performance computing centers (HPCCs). Representatives from fifteen high-performance computing (HPC) organizations, four HPC vendor partners, and three government agencies attended the workshop. The overall workshop findings were: (1) Standard risk management techniques and tools are in the aggregate applicable to projects at HPCCs and are commonly employed by the HPC community; (2) HPC projects have characteristics that necessitate a tailoring of the standard risk management practices; (3) All HPCC acquisition projects can benefit by employing risk management, but the specific choice of risk management processes and tools is less important to the success of the project; (4) The special relationship between the HPCCs and HPC vendors must be reflected in the risk management strategy; (5) Best practices findings include developing a prioritized risk register with special attention to the top risks, establishing a practice of regular meetings and status updates with the platform partner, supporting regular and open reviews that engage the interests and expertise of a wide range of staff and stakeholders, and documenting and sharing the acquisition/build/deployment experience; and (6) Top risk categories include system scaling issues, request for proposal/contract and acceptance testing, and

Outline of criticality safety research project

International Nuclear Information System (INIS)

Kobayashi, Iwao; Tachimori, Shoichi; Suzaki, Takenori; Takeshita, Isao; Miyoshi, Yoshinori; Nakajima, Ken; Sakurai, Satoshi; Yanagisawa, Hiroshi

1987-01-01

As the power generation capacity of LWRs in Japan increased, the establishment and development of nuclear fuel cycle have become the important subject. Conforming to the safety research project of the nation, the Japan Atomic Energy Research Institute has advanced the project of constructing a new research facility, that is, Nuclear Fuel Cycle Engineering Research Facility (NUCEF). In this facility, it is planned to carry out the research on criticality safety, upgraded reprocessing techniques, and the treatment and disposal of transuranium element wastes. In this paper, the subjects of criticality safety research and the research carried out with a criticality safety experiment facility which is expected to be installed in the NUCEF are briefly reported. The experimental data obtained from the criticality safety handbooks and published literatures in foreign countries are short of the data on the mixture of low enriched uranium and plutonium which is treated in the reprocessing of spent fuel from LWRs. The acquisition of the criticality data for various forms of fuel, the elucidation of the scenario of criticality accidents, and the soundness of the confinement system for gaseous fission products and plutonium are the main subjects. The Static Criticality Safety Facility, Transient Criticality Safety Facility and pulse column system are the main facilities. (Kako, I.)

UMTRA Project environmental, health, and safety plan

International Nuclear Information System (INIS)

1989-02-01

The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

Understanding lean & safety projects: analysis of case studies

Directory of Open Access Journals (Sweden)

Maria Crema

2017-12-01

Full Text Available Facing the current socio-economic contingency while guaranteeing a high level of care quality is particularly challenging in the field of healthcare. Through an integrated adoption of emerging managerial solutions, projects that allow organizations to achieve both efficiency and patient safety improvements could be implemented, thereby transposing policy directives towards a safer and more sustainable healthcare system. Therefore, the purpose of this paper is to investigate the features of Lean & Safety (L&S projects. Three Health Lean Management (HLM projects that had unexpected patient safety results were selected from the same region. Differences and similarities among the cases have been highlighted and interesting points of evidence have been noted. Despite the fact that the projects were pursuing similar objectives and benefiting from comparable support, the obtained changes had direct impact on patient safety enhancement in the cases that involved the front-office processes, and an indirect impact on patient safely for the L&S project that focused on back-office activities. The implementation processes and the Information and Communication Technologies (ICT adoption of the cases are also different.

The QED Workshop

Energy Technology Data Exchange (ETDEWEB)

Pieper, G.W.

1994-07-01

On May 18--20, 1994, Argonne National Laboratory hosted the QED Workshop. The workshop was supported by special funding from the Office of Naval Research. The purpose of the workshop was to assemble of a group of researchers to consider whether it is desirable and feasible to build a proof-checked encyclopedia of mathematics, with an associated facility for theorem proving and proof checking. Among the projects represented were Coq, Eves, HOL, ILF, Imps, MathPert, Mizar, NQTHM, NuPrl, OTTER, Proof Pad, Qu-Prolog, and RRL. Although the content of the QED project is highly technical rigorously proof-checked mathematics of all sorts the discussions at the workshop were rarely technical. No prepared talks or papers were given. Instead, the discussions focused primarily on such political, sociological, practical, and aesthetic questions, such as Why do it? Who are the customers? How can one get mathematicians interested? What sort of interfaces are desirable? The most important conclusion of the workshop was that QED is an idea worthy pursuing, a statement with which virtually all the participants agreed. In this document, the authors capture some of the discussions and outline suggestions for the start of a QED scientific community.

Workshop meeting

International Nuclear Information System (INIS)

Veland, Oeystein

2004-04-01

1-2 September 2003 the Halden Project arranged a workshop on 'Innovative Human-System Interfaces and their Evaluation'. This topic is new in the HRP 2003-2005 programme, and it is important to get feedback from member organizations to the work that is being performed in Halden. It is also essential that relevant activities and experiences in this area from the member organizations are shared with the Halden staff and other HRP members. Altogether 25 persons attended the workshop. The workshop had a mixture of presentations and discussions, and was chaired by Dominique Pirus of EDF, France. Day one focused on the HRP/IFE activities on Human-System Interface design, including Function-oriented displays, Ecological Interface Design, Task-oriented displays, as well as work on innovative display solutions for the oil and gas domain. There were also presentations of relevant work in France, Japan and the Czech Republic. The main focus of day two was the verification and validation of human-system interfaces, with presentations of work at HRP on Human-Centered Validation, Criteria-Based System Validation, and Control Room Verification and Validation. The chairman concluded that it was a successful workshop, although one could have had more time for discussions. The Halden Project got valuable feedback and viewpoints on this new topic during the workshop, and will consider all recommendations related to the future work in this area. (Author)

A Fire Safety Certification System for Board and Care Operators and Staff. SBIR Phase II: Final Report.

Science.gov (United States)

Walker, Bonnie L.

This report describes Phase II of a project which developed a system for delivering fire safety training to board and care providers who serve adults with developmental disabilities. Phase II focused on developing and pilot testing a "train the trainers" workshop for instructors and field testing the provider's workshop. Evaluation of…

Joint WHO/ISH workshop on efficacy and radiation safety in interventional radiology

International Nuclear Information System (INIS)

Baeuml, A.; Bauer, B.; Bernhardt, J.H.; Stieve, F.E.; Veit, R.; Zeitlberger, I.

1997-02-01

With the constantly developing technology and the opening of new fields of application, the implementation of Interventional Radiology (IR) is increasing considerably. These sophisticated procedures can frequently replace open surgery, and this is of enormous benefit for the patient. On the other hand, IR involves prolonged application of fluoroscopy and - due to the need for excellent image quality - partly very high dose-rate levels. Additionally, cine-series, and alsogreat numbers of single radiographs are necessary. Accordingly, the levels of exposure to patients and staff are very high. In order to consider possible reduction of the radiation risks of IR procedures interdiciplinary talks between representatives of manufacturers of X-ray equipment, hospital physicists and the clinical community would seem necessary in order to find ways of avoiding unproductive radiation exposure to the patient and to clinical staff. This was the aim of a workshop on IR, which was jointly organized by the World Health Organization and the Institute of Radiation Hygiene of the Federal Office for Radiation Protection in Germany in October 1995. It was intended as a forum for the discussion of issues related to IR, and to forster improved application, that is to say as an opportunity: To present the state of the art; to work out proposals for more efficient clinical protocols; to discuss on schemes of education and training and on equipment-related developments. Improvement of radiation safety for both patients and staff, was the general aim of the workshop. This volume contains the presentations given on the first day of the workshop. (orig./DG) [de

North Region ROW tool implementation workshop.

Science.gov (United States)

2010-08-02

Welcome to the North Region ROW Tool Workshop. This workshop is funded under an implementation project sponsored by TxDOTs Research & Technology Implementation Office (RTI). This is the second of four regional workshops being planned for this summ...

The Role of the Engineered Barrier System in Safety Cases for Geological Radioactive Waste Repositories: An NEA Initiative in Co-Operations with the EC Process Issues and Modeling

International Nuclear Information System (INIS)

D.G. Bennett; A.J. Hooper; S. Voinis; H. Umeki; A.V. Luik; J. Alonso

2006-01-01

The Integration Group for the Safety Case (IGSC) of the Nuclear Energy Agency (NEA) Radioactive Waste Management Committee in co-operation with the European Commission (EC) is conducting a project to develop a greater understanding of how to achieve the necessary integration for successful design, construction, testing, modeling, and assessment of engineered barrier systems. The project also seeks to clarify the role that the EBS plays in assuring the overall safety of a repository. A framework for the EBS Project is provided by a series of workshops that allow discussion of the wide range of activities necessary for the design, assessment and optimization of the EBS, and the integration of this information into the safety case. The topics of this series of workshops have been planned so that the EBS project will work progressively through the main aspects comprising one cycle of the design and optimization process. This paper seeks to communicate key results from the EBS project to a wider audience. The paper focuses on two topics discussed at the workshops: process issues and the role of modeling

Spent Nuclear Fuel Project Safety Management Plan

International Nuclear Information System (INIS)

Garvin, L.J.

1996-02-01

The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

Advanced nuclear reactor safety issues and research needs

International Nuclear Information System (INIS)

2002-01-01

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

MATHEMATICAL APPARATUS FOR KNOWLEDGE BASE PROJECT MANAGEMENT OF OCCUPATIONAL SAFETY

Directory of Open Access Journals (Sweden)

Валентина Николаевна ПУРИЧ

2015-05-01

Full Text Available The occupational safety project (OSP management is aimed onto a rational choice implementation. With respect to the subjectivity of management goals the project selection is considered as a minimum formalization level information process, The proposed project selection model relies upon the enterprise’s occupational and industrial safety assessment using fuzzy logic and linguistic variables based on occupational safety knowledge base.

Human Genome Diversity Project. Summary of planning workshop 3(B): Ethical and human-rights implications

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-12-31

The third planning workshop of the Human Genome Diversity Project was held on the campus of the US National Institutes of Health in Bethesda, Maryland, from February 16 through February 18, 1993. The second day of the workshop was devoted to an exploration of the ethical and human-rights implications of the Project. This open meeting centered on three roundtables, involving 12 invited participants, and the resulting discussions among all those present. Attendees and their affiliations are listed in the attached Appendix A. The discussion was guided by a schedule and list of possible issues, distributed to all present and attached as Appendix B. This is a relatively complete, and thus lengthy, summary of the comments at the meeting. The beginning of the summary sets out as conclusions some issues on which there appeared to be widespread agreement, but those conclusions are not intended to serve as a set of detailed recommendations. The meeting organizer is distributing his recommendations in a separate memorandum; recommendations from others who attended the meeting are welcome and will be distributed by the meeting organizer to the participants and to the Project committee.

Criticality safety benchmark evaluation project: Recovering the past

Energy Technology Data Exchange (ETDEWEB)

Trumble, E.F.

1997-06-01

A very brief summary of the Criticality Safety Benchmark Evaluation Project of the Westinghouse Savannah River Company is provided in this paper. The purpose of the project is to provide a source of evaluated criticality safety experiments in an easily usable format. Another project goal is to search for any experiments that may have been lost or contain discrepancies, and to determine if they can be used. Results of evaluated experiments are being published as US DOE handbooks.

Specific environmental release categories--A tool for improving chemical safety assessment in the EC--report of a multi-stakeholder workshop.

Science.gov (United States)

Sättler, Daniel; Schnöder, Frank; Aust, Nannett; Ahrens, Andreas; Bögi, Christian; Traas, Theo; Tolls, Johannes

2012-10-01

In April 2011, experts from industry and authorities met for a workshop to discuss experience and future developments regarding the use of specific environmental release categories (SPERCs) in chemicals safety assessment (CSA) under the European Chemicals Regulation Registration, Evaluation and Authorization of Chemicals (REACH). This article provides a summary of the workshop. It briefly explains what a SPERC is, why SPERCs are needed, where the challenges of the concept are, and what improvements are needed to make SPERCs a useful tool for assessments under REACH. Copyright © 2012 SETAC.

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

International Nuclear Information System (INIS)

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

1998-01-01

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

CFD for Nuclear Reactor Safety Applications (CFD4NRS-4) - Workshop Proceedings

International Nuclear Information System (INIS)

2014-01-01

papers given at the Workshop covered different nuclear safety topics, and, for the first time, some reactor-design issues. However, the ratio of papers devoted to experimentation to those devoted to analysis was not as well balanced as previously seen, with too few experimental studies reported. The session topics were wide and various, including advanced reactor modelling, flow mixing issues, boiling and condensation modelling, multi-phase and multi-physics problems, containment analysis, plant application, hydrogen transport and fires, advanced measuring techniques, and single and multiphase flow in rod bundles. This paper only provides the list of presentations and the summary of the technical sessions

WALLTURB International Workshop

CERN Document Server

Jimenez, Javier; Marusic, Ivan

2011-01-01

This book brings together selected contributions from the WALLTURB workshop on ”Understanding and modelling of wall turbulence” held in Lille, France, on April 21st to 23rd 2009. This workshop was organized by the WALLTURB consortium, in order to present to the relevant scientific community the main results of the project and to stimulate scientific discussions around the subject of wall turbulence. The workshop reviewed the recent progress in theoretical, experimental and numerical approaches to wall turbulence. The problems of zero pressure gradient, adverse pressure gradient and separating turbulent boundary layers were addressed in detail with the three approaches, using the most advanced tools. This book is a milestone in the research field, thanks to the high level of the invited speakers and the involvement of the contributors and a testimony of the achievement of the WALLTURB project.

Rapporteur's Report of the Workshop on Radiological Characterisation for Decommissioning

International Nuclear Information System (INIS)

Thierfeldt, Stefan

2012-01-01

In April 2012, the Nuclear Energy Agency, in co-operation with Studsvik Nuclear AB, the Swedish Radiation Safety Authority (SSM), Swedish Nuclear Fuel and Waste Management Company (SKB) and AB SVAFO, held a Workshop on Radiological Characterisation in Decommissioning in Studsvik near Nykoeping (Sweden). During three days, a wide range of presentations, posters, discussions and site visits brought together over 120 participants from 23 countries and 4 international organisations, the IAEA, the WNA, the European Commission and the OECD/NEA. Members of the Task Group on Radiological Characterisation for Decommissioning (RCD) of the WPDD were involved in the preparation of the workshop. Many decommissioning projects of all types of nuclear installations have progressed substantially and/or have been completed to brown field or green field conditions, so that it was the right time to bring together operators, regulators, scientists, consultants and contractors to exchange information and views and to evaluate the information on radiological characterisation gained from this multitude of projects. The outcome will be valuable for the large number of decommissioning projects about to start in the near future. The Workshop consisted of 5 topical sessions and a poster session. The topical sessions were complemented by discussions in the plenary and in smaller groups. This report provides a short summary of the various presentations and discussions. It concentrates on the outcome of the presentations, posters and discussions than giving an account of the spoken word

Relational approach in managing construction project safety: a social capital perspective.

Science.gov (United States)

Koh, Tas Yong; Rowlinson, Steve

2012-09-01

Existing initiatives in the management of construction project safety are largely based on normative compliance and error prevention, a risk management approach. Although advantageous, these approaches are not wholly successful in further lowering accident rates. A major limitation lies with the approaches' lack of emphasis on the social and team processes inherent in construction project settings. We advance the enquiry by invoking the concept of social capital and project organisational processes, and their impacts on project safety performance. Because social capital is a primordial concept and affects project participants' interactions, its impact on project safety performance is hypothesised to be indirect, i.e. the impact of social capital on safety performance is mediated by organisational processes in adaptation and cooperation. A questionnaire survey was conducted within Hong Kong construction industry to test the hypotheses. 376 usable responses were received and used for analyses. The results reveal that, while the structural dimension is not significant, the mediational thesis is generally supported with the cognitive and relational dimensions affecting project participants' adaptation and cooperation, and the latter two processes affect safety performance. However, the cognitive dimension also directly affects safety performance. The implications of these results for project safety management are discussed. Copyright © 2011 Elsevier Ltd. All rights reserved.

HTTR workshop (workshop on hydrogen production technology)

International Nuclear Information System (INIS)

Shiina, Yasuaki; Takizuka, Takakazu

2004-12-01

Various research and development efforts have been performed to solve the global energy and environmental problems caused by large consumption of fossil fuels. Research activities on advanced hydrogen production technology by the use of nuclear heat from high temperature gas cooled reactors, for example, have been flourished in universities, research institutes and companies in many countries. The Department of HTTR Project and the Department of Advanced Nuclear Heat Technology of JAERI held the HTTR Workshop (Workshop on Hydrogen Production Technology) on July 5 and 6, 2004 to grasp the present status of R and D about the technology of HTGR and the nuclear hydrogen production in the world and to discuss about necessity of the nuclear hydrogen production and technical problems for the future development of the technology. More than 110 participants attended the Workshop including foreign participants from USA, France, Korea, Germany, Canada and United Kingdom. In the Workshop, the presentations were made on such topics as R and D programs for nuclear energy and hydrogen production technologies by thermo-chemical or other processes. Also, the possibility of the nuclear hydrogen production in the future society was discussed. The workshop showed that the R and D for the hydrogen production by the thermo-chemical process has been performed in many countries. The workshop affirmed that nuclear hydrogen production could be one of the competitive supplier of hydrogen in the future. The second HTTR Workshop will be held in the autumn next year. (author)

Human Brain Proteome Project - 12th HUPO BPP Workshop. 26 September 2009, Toronto, Canada.

Science.gov (United States)

Gröttrup, Bernd; Eisenacher, Martin; Stephan, Christian; Marcus, Katrin; Lee, Bonghee; Meyer, Helmut E; Park, Young Mok

2010-06-01

The HUPO Brain Proteome Project (HUPO BPP) held its 12th workshop in Toronto on 26 September 2009 prior to the HUPO VIII World Congress. The principal aim of this project is to obtain a better understanding of neurodiseases and ageing, with the ultimate objective of discovering prognostic and diagnostic biomarkers, in addition to the development of novel diagnostic techniques and new medications. The attendees came together to discuss progress in the human clinical neuroproteomics and to define the needs and guidelines required for more advanced proteomic approaches.

Assessment of Contributions to Patient Safety Knowledge by the Agency for Healthcare Research and Quality-Funded Patient Safety Projects

Science.gov (United States)

Sorbero, Melony E S; Ricci, Karen A; Lovejoy, Susan; Haviland, Amelia M; Smith, Linda; Bradley, Lily A; Hiatt, Liisa; Farley, Donna O

2009-01-01

Objective To characterize the activities of projects funded in Agency for Healthcare Research and Quality (AHRQ)' patient safety portfolio and assess their aggregate potential to contribute to knowledge development. Data Sources Information abstracted from proposals for projects funded in AHRQ' patient safety portfolio, information on safety practices from the AHRQ Evidence Report on Patient Safety Practices, and products produced by the projects. Study Design This represented one part of the process evaluation conducted as part of a longitudinal evaluation based on the Context–Input–Process–Product model. Principal Findings The 234 projects funded through AHRQ' patient safety portfolio examined a wide variety of patient safety issues and extended their work beyond the hospital setting to less studied parts of the health care system. Many of the projects implemented and tested practices for which the patient safety evidence report identified a need for additional evidence. The funded projects also generated a substantial body of new patient safety knowledge through a growing number of journal articles and other products. Conclusions The projects funded in AHRQ' patient safety portfolio have the potential to make substantial contributions to the knowledge base on patient safety. The full value of this new knowledge remains to be confirmed through the synthesis of results. PMID:21456108

Workshop on PSA for New and Advanced Reactors

International Nuclear Information System (INIS)

2012-01-01

This workshop was organized by the NEA Working Group on Risk Assessment (WGRISK). The key objective of the workshop was to share the current state-of-the art on the PSA (Probabilistic Safety Assessment) applied for new reactors and advanced reactors. Fifty experts from 13 countries and one international organization (IAEA) participated in the present workshop, and 35 technical papers were presented. The main topics of interest, discussed during the workshop, included the followings: regulatory aspects, risk-informed methods, technical aspects of the PSA for new and advanced reactors, hazards of PSA (internal and external), severe accident/source term/Level 2 PSA, and consequence analysis/Level 3 PSA. Among the technical aspects of the PSA, the assessment of the reliability of passive safety systems appears to be a recurrent issue

Workshop proceedings: "We are the Olifants" - Key stakeholder workshop for the Upper Olifants River study

CSIR Research Space (South Africa)

Funke, Nicola S

2013-03-31

Full Text Available Project Leader, Natural Resources and the Environment Council for Scientific and Industrial Research March 2013 Workshop Proceedings Page v EXECUTIVE SUMMARY The Upper Olifants Key Stakeholder Workshop took place at the CSIR Knowledge...

Texas RPO workshop implementation project summary.

Science.gov (United States)

2012-05-01

This report documents rural planning organization (RPO) workshops conducted throughout Texas. An RPO is a voluntary organization created and governed by locally elected officials responsible for transportation decisions at the local level. RPOs addre...

Report on the workshop to review waste inventory, waste characteristics and reference site candidates

International Nuclear Information System (INIS)

1997-07-01

There is a need of co-operation among Regional Co-operative Agreement (RCA) Member States in the field of low and intermediate level waste (LILW) disposal. An integrated approach is essential for successful establishment of LILW disposal facilities in RCA Member States. This would include: a) identification of waste inventory and characteristics; b) guidelines for implementation of LILW disposal; c) regulatory guidelines; d) safety assessment; e) quality assurance; and f) public acceptance. This project will focus on technical issues. The overall objective of the project, established in the project formulation meeting, is to assist RCA Member States in establishing national disposal activities for radioactive waste from nuclear applications by providing expert advice and training on techniques and methodology associated with planning and establishment of disposal facilities and to obtain improved knowledge of key staff members for the implementation of LILW disposal. The purpose of this workshop was to identify waste inventories, waste characteristics, site characteristics (generic or site specific) for disposal of LILW in RCA Member States of the project and identify conceptual reference site conditions and consider reference repository concepts preliminarily. Also the workshop was to establish an action plan of the next step. The workshop was held in Shanghai, China from 7 to 9 July 1997 and attended by 7 countries, i.e. Australia, China, Indonesia, Japan, Republic of Korea, Sri Lanka and Thailand. Refs, figs, tabs

Opening Session - Introductory remarks for Workshop on Accident Tolerant Fuel. OECD/NEA Workshop on Accident Tolerant Fuels, Workshop Expectations

International Nuclear Information System (INIS)

Dujardin, Thierry; Gulliford, Jim; Massara, Simone; Pasamehmetoglu, K.

2013-01-01

The workshop opened with the welcome address from Th. Dujardin (OECD/NEA), NEA Deputy Director. Th. Dujardin recalled the integrated NEA response to the dramatic Fukushima-Daiichi events performed by three standing technical committees: the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH). J. Gulliford (OECD/NEA) placed the workshop in the context of the activities of the Nuclear Science Committee within the framework of the NEA response to Fukushima- Daiichi. K. Pasamehmetoglu (INL, US) explained the main goals of the workshop oriented towards defining requirements for selection among various options during the feasibility phase of the development process, and not towards identifying and proposing design solutions

The International Criticality Safety Benchmark Evaluation Project

International Nuclear Information System (INIS)

Briggs, B. J.; Dean, V. F.; Pesic, M. P.

2001-01-01

In order to properly manage the risk of a nuclear criticality accident, it is important to establish the conditions for which such an accident becomes possible for any activity involving fissile material. Only when this information is known is it possible to establish the likelihood of actually achieving such conditions. It is therefore important that criticality safety analysts have confidence in the accuracy of their calculations. Confidence in analytical results can only be gained through comparison of those results with experimental data. The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the US Department of Energy. The project was managed through the Idaho National Engineering and Environmental Laboratory (INEEL), but involved nationally known criticality safety experts from Los Alamos National Laboratory, Lawrence Livermore National Laboratory, Savannah River Technology Center, Oak Ridge National Laboratory and the Y-12 Plant, Hanford, Argonne National Laboratory, and the Rocky Flats Plant. An International Criticality Safety Data Exchange component was added to the project during 1994 and the project became what is currently known as the International Criticality Safety Benchmark Evaluation Project (ICSBEP). Representatives from the United Kingdom, France, Japan, the Russian Federation, Hungary, Kazakhstan, Korea, Slovenia, Yugoslavia, Spain, and Israel are now participating on the project In December of 1994, the ICSBEP became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency's (OECD-NEA) Nuclear Science Committee. The United States currently remains the lead country, providing most of the administrative support. The purpose of the ICSBEP is to: (1) identify and evaluate a comprehensive set of critical benchmark data; (2) verify the data, to the extent possible, by reviewing original and subsequently revised documentation, and by talking with the

Stimulation of ICT/domotics in houses. The organization of 2 workshops. Final report; De bevordering van ICT/domotica in woningen. De organisatie van 2 workshops. Eindrapport

Energy Technology Data Exchange (ETDEWEB)

Romer, J.C. [ECN Duurzame Energie in de Gebouwde Omgeving DEGO, Petten (Netherlands)

2003-07-01

The title project concerns the organization of two workshops on two concrete projects: (1) a building project for 43 dwellings for elderly people in Anna Paulowna, Netherlands, and (2) the building of a home for the elderly people (called Parkzicht) in Hippolytushoef, Netherlands. Preparatory activities for and the organization of the two workshops are described. The first workshop was held October 4th, 2002. The second workshop was planned for December 13th, 2002, but was cancelled. [Dutch] Een overzicht wordt gegeven van de activiteiten die hebben plaatsgevonden rond 2 concreet te realiseren projecten in Noord-Holland. De activiteiten bestaan uit de voorbereidende activiteiten en de organisatie van twee workshops. Een van de projecten betreft de bouw van 43 woningen voor senioren in Anna Paulowna en het andere project betreft de bouw van het verzorgingstehuis Parkzicht in Hippolytushoef. De 'Anna Paulowna' workshop werd 4 oktober 2002 gehouden. De Hippolytushoef workshop was gepland op 13 december 2002 maar is niet doorgegaan.

Safety culture and subcontractor network governance in a complex safety critical project

International Nuclear Information System (INIS)

Oedewald, Pia; Gotcheva, Nadezhda

2015-01-01

In safety critical industries many activities are currently carried out by subcontractor networks. Nevertheless, there are few studies where the core dimensions of resilience would have been studied in safety critical network activities. This paper claims that engineering resilience into a system is largely about steering the development of culture of the system towards better ability to anticipate, monitor, respond and learn. Thus, safety culture literature has relevance in resilience engineering field. This paper analyzes practical and theoretical challenges in applying the concept of safety culture in a complex, dynamic network of subcontractors involved in the construction of a new nuclear power plant in Finland, Olkiluoto 3. The concept of safety culture is in focus since it is widely used in nuclear industry and bridges the scientific and practical interests. This paper approaches subcontractor networks as complex systems. However, the management model of the Olkiluoto 3 project is to a large degree a traditional top-down hierarchy, which creates a mismatch between the management approach and the characteristics of the system to be managed. New insights were drawn from network governance studies. - Highlights: • We studied a relevant topical subject safety culture in nuclear new build project. • We integrated safety science challenges and network governance studies. • We produced practicable insights in managing safety of subcontractor networks

Key Findings from the U.S.-India Partnership for Climate Resilience Workshop on Development and Application of Downscaling Climate Projections

Science.gov (United States)

Kunkel, K.; Dissen, J.; Easterling, D. R.; Kulkarni, A.; Akhtar, F. H.; Hayhoe, K.; Stoner, A. M. K.; Swaminathan, R.; Thrasher, B. L.

2017-12-01

s part of the Department of State U.S.-India Partnership for Climate Resilience (PCR), scientists from NOAA NCEI, CICS-NC, Texas Tech University (TTU), Stanford University (SU), and the Indian Institute of Tropical Meteorology (IITM) held a workshop at IITM in Pune, India during 7-9 March 2017 on the development, techniques and applications of downscaled climate projections. Workshop participants from TTU, SU, and IITM presented state-of-the-art climate downscaling techniques using the ARRM method, NASA NEX climate products, CORDEX-South Asia and analysis tools for resilience planning and sustainable development. PCR collaborators in attendance included Indian practitioners, researchers and other NGO including the WRI Partnership for Resilience and Preparedness (PREP), The Energy and Resources Institute (TERI), and NIH. The scientific techniques were provided to workshop participants in a software package written in R by TTU scientists and several sessions were devoted to hands-on experience with the software package. The workshop further examined case studies on the use of downscaled climate data for decision making in a range of sectors, including human health, agriculture, and water resources management as well as to inform the development of the India State Action Plans. This talk will discuss key outcomes including information needs for downscaling climate projections, importance of QA/QC of the data, key findings from select case studies, and the importance of collaborations and partnerships to apply downscaling projections to help inform the development of the India State Action Plans.

Nuclear Safety Project - annual report 1980

International Nuclear Information System (INIS)

1981-08-01

The Annual Report 1980 is a detailed description (in German language) of work within the Nuclear Safety Project performed in 1980 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes for each individual research activity short summaries in English language on work completed, essential results, plans for the near future. (orig./RW) [de

Summary of the Second Workshop on Liquid Argon Time Projection Chamber Research and Development in the United States

CERN Document Server

Acciarri, R; Artrip, D; Baller, B; Bromberg, C; Cavanna, F; Carls, B; Chen, H; Deptuch, G; Epprecht, L; Dharmapalan, R; Foreman, W; Hahn, A; Johnson, M; Jones, B J P; Junk, T; Lang, K; Lockwitz, S; Marchionni, A; Mauger, C; Montanari, C; Mufson, S; Nessi, M; Back, H Olling; Petrillo, G; Pordes, S; Raaf, J; Rebel, B; Sinins, G; Soderberg, M; Spooner, N J C; Stancari, M; Strauss, T; Terao, K; Thorn, C; Tope, T; Toups, M; Urheim, J; Van de Water, R; Wang, H; Wasserman, R; Weber, M; Whittington, D; Yang, T

2015-01-01

The second workshop to discuss the development of liquid argon time projection chambers (LArTPCs) in the United States was held at Fermilab on July 8-9, 2014. The workshop was organized under the auspices of the Coordinating Panel for Advanced Detectors, a body that was initiated by the American Physical Society Division of Particles and Fields. All presentations at the workshop were made in six topical plenary sessions: $i)$ Argon Purity and Cryogenics, $ii)$ TPC and High Voltage, $iii)$ Electronics, Data Acquisition and Triggering, $iv)$ Scintillation Light Detection, $v)$ Calibration and Test Beams, and $vi)$ Software. This document summarizes the current efforts in each of these areas. It primarily focuses on the work in the US, but also highlights work done elsewhere in the world.

Summary of the Second Workshop on Liquid Argon Time Projection Chamber Research and Development in the United States

Energy Technology Data Exchange (ETDEWEB)

Acciarri, R. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); et al.

2015-04-21

The second workshop to discuss the development of liquid argon time projection chambers (LArTPCs) in the United States was held at Fermilab on July 8-9, 2014. The workshop was organized under the auspices of the Coordinating Panel for Advanced Detectors, a body that was initiated by the American Physical Society Division of Particles and Fields. All presentations at the workshop were made in six topical plenary sessions: i) Argon Purity and Cryogenics, ii) TPC and High Voltage, iii) Electronics, Data Acquisition and Triggering, iv) Scintillation Light Detection, v) Calibration and Test Beams, and vi) Software. This document summarizes the current efforts in each of these areas. It primarily focuses on the work in the US, but also highlights work done elsewhere in the world.

Activities of ARCAL XX for the development of guidelines for the safety of radiation sources

International Nuclear Information System (INIS)

Velasques de Oliveira, S.M.; Betancourt, L.A.

2001-01-01

This report presents the contribution of the ARCAL XX project 'Guidelines for the Control of Radiation Sources' for the development and harmonization of the safety of radiation sources in Latin America. The project began in 1997 with the participation of nine countries. The methodology adopted has enabled all experts from the nine countries involved in the project to participate in discussions on the development of guidelines based on regional experience. Three common documents for all practices and six safety guides for the main practices have been revised for publication. For the next two years, the project co-ordinators are proposing regional and national workshops for the application of the safety guides approved by the ARCAL programme. (author)

The Hospital Microbiome Project: Meeting Report for the 1st Hospital Microbiome Project Workshop on sampling design and building science measurements, Chicago, USA, June 7th-8th 2012.

Science.gov (United States)

Smith, Daniel; Alverdy, John; An, Gary; Coleman, Maureen; Garcia-Houchins, Sylvia; Green, Jessica; Keegan, Kevin; Kelley, Scott T; Kirkup, Benjamin C; Kociolek, Larry; Levin, Hal; Landon, Emily; Olsiewski, Paula; Knight, Rob; Siegel, Jeffrey; Weber, Stephen; Gilbert, Jack

2013-04-15

This report details the outcome of the 1st Hospital Microbiome Project workshop held on June 7th-8th, 2012 at the University of Chicago, USA. The workshop was arranged to determine the most appropriate sampling strategy and approach to building science measurement to characterize the development of a microbial community within a new hospital pavilion being built at the University of Chicago Medical Center. The workshop made several recommendations and led to the development of a full proposal to the Alfred P. Sloan Foundation as well as to the creation of the Hospital Microbiome Consortium.

How stakeholders view the use of analogues in safety cases: PAMINA

International Nuclear Information System (INIS)

Atherton, Elizabeth; Bailey, Lucy

2008-01-01

The aim of this presentation is to provide an overview of some research that has been undertaken in the UK to investigate stakeholders' views of analogues. There are various reasons for using analogues including: to try and explain difficult concepts; to compare disposal facility features with familiar and/or natural systems; to provide an alternative, non-numerical line of reasoning to support the Safety Case conclusions; to provide evidence of behaviour over very long timescales, that cannot be achieved in the laboratory. There are some dangers when using analogues that people should be aware of: the analogue conditions may not be the same as those found in a disposal facility, so the analogue may have limited application. Some analogues may have negative implications, for example artefacts that have corroded. Analogues can be taken too far and used in inappropriate ways to try and support an assumption. So it is important to find out how stakeholders view the use of analogues in a safety case. NDA is involved in an EC funded project called Pamina (Performance Assessment Methodologies in Application). The project involves 26 partners from 11 European countries, plus other associated members and runs for 3 years from October 2006 to October 2009. The NDA is involved in several parts of the project: Exploring issues of modelling uncertainty; Evaluating effectiveness of approaches for communicating safety cases with stakeholders. NDA ran a workshop in October 2007 in Manchester. The aims of the workshop were to explore how different methods of communicating aspects of a safety case were received by stakeholders. The workshop presented stakeholders with: Examples of different repository concepts; Descriptions of barrier performance; Different ways of presenting numerical results; Use of natural analogues

Customer/User Workshops in Product development

DEFF Research Database (Denmark)

Brandt, Eva; Binder, Thomas

1997-01-01

In a recent product development project, we have taken part in establishing and organising a series of workshops with a group of customers/users of a future product line through out the development project. The workshops is a kind of informal meetingplace for engineering, marketing, customers...... and discuss experiences with this kind of collaborative fora. We have tried to demonstrate that having an on-going dialogue with users/customers also during detailed design in not only a means to keep 'the voive of the customer alive'. We have found that the workshops have an important impact on securing...

Workshop report: US-China workshop on smart structures and smart systems

Science.gov (United States)

Tomizuka, Masayoshi

2006-03-01

A Joint U.S.-China workshop on the topic of Integrated Sensing Systems, Mechatronics and Smart Structures Technologies was held in Jinan, China in October 2005 to evaluate the current status of research and education in the topic areas in the United States and China, to identify critical and strategic research and educational issues of mutual interest, and to identify joint research projects and potential research teams for collaborative research activities. The workshop included a series of presentations by leading researchers and educators from the United States and China and group discussions on the workshop objectives.

Joint road safety operations in tunnels and open roads

Science.gov (United States)

Adesiyun, Adewole; Avenoso, Antonio; Dionelis, Kallistratos; Cela, Liljana; Nicodème, Christophe; Goger, Thierry; Polidori, Carlo

2017-09-01

The objective of the ECOROADS project is to overcome the barrier established by the formal interpretation of the two Directives 2008/96/EC and 2004/54/EC, which in practice do not allow the same Road Safety Audits/Inspections to be performed inside tunnels. The projects aims at the establishment of a common enhanced approach to road infrastructure and tunnel safety management by using the concepts and criteria of the Directive 2008/96/CE on road infrastructure safety management and the results of related European Commission (EC) funded projects. ECOROADS has already implemented an analysis of national practices regarding Road Safety Inspections (RSI), two Workshops with the stakeholders, and an exchange of best practices between European tunnel experts and road safety professionals, which led to the definition of common agreed safety procedures. In the second phase of the project, different groups of experts and observers applied the above common procedures by inspecting five European road sections featuring both open roads and tunnels in Belgium, Albania, Germany, Serbia and Former Yugoslav Republic of Macedonia. This paper shows the feedback of the 5 joint safety operations and how they are being used for a set of - recommendations and guidelines for the application of the RSA and RSI concepts within the tunnel safety operations.

2012 right-of-way fatality & trespass prevention workshop

Science.gov (United States)

2013-04-30

Based on the success of the 2008 Trespasser Workshop, FRA and FTA sponsored this follow-on workshop. The keynote speech by FRA Administrator, Mr. Joseph C. Szabo, was followed by 23 technical presentations in the areas of Pedestrian Safety, Hazard Ma...

Proceedings of the GNWT Beaufort-Delta regional workshop on the social impacts of the Mackenzie Valley Gas Project

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This workshop provided a forum for communities and governments to discuss the potential social impacts of the Mackenzie Gas Project (MGP). The purpose of the workshop was to ensure that communities will have the capacity to manage the social impacts of the pipeline and related exploration and development activities in the future. The workshop was organized around key questions that solicited community perspectives on social impacts from various governmental agencies. The construction of the MGP will result in increased needs for housing, medical services, and social work programs in affected communities. It is expected that construction camps located near communities will create the need for additional drug abuse, and domestic violence counsellors. Inventories of social programs and baseline profiles of social conditions were presented. Local plans for managing impacts during construction of the MGP were discussed, and potential mitigation efforts were reviewed. Issues related to funding and social assistance were also examined. It was concluded that the workshop will serve as the basis for future collaboration and cooperation amongst the various levels of government in managing the social impacts of the pipeline. Six presentations were given at the workshop. refs., tabs., figs.

Krsko periodic safety review project prioritization process

International Nuclear Information System (INIS)

Basic, I.; Vrbanic, I.; Spiler, J.; Lambright, J.

2004-01-01

Definition of a Krsko Periodic Safety Review (PSR) project is a comprehensive safety review of a plant after last ten years of operation. The objective is a verification by means of a comprehensive review using current methods that Krsko NPP remains safety when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. This objective encompasses the three main criteria or goals: confirmation that the plant is as safe as originally intended, determination if there are any structures, systems or components that could limit the life of the plant in the foreseeable future, and comparison the plant against modern safety standards and to identify where improvements would be beneficial at justifiable cost. Krsko PSR project is structured in the three phases: Phase 1: Preparation of Detailed 10-years PSR Program, Phase 2: Performing of 10-years PSR Program and preparing of associated documents (2001-2003), and Phase 3: Implementation of the prioritized compensatory measures and modifications (development of associated EEAR, DMP, etc.) after agreement with the SNSA on the design, procedures and time-scales (2004-2008). This paper presents the NEK PSR results of work performed under Phase 2 focused on the ranking of safety issues and prioritization of corrective measures needed for establishing an efficient action plan. Safety issues were identified in Phase 2 during the following review processes: Periodic Safety Review (PSR) task; Krsko NPP Regulatory Compliance Program (RCP) review; Westinghouse Owner Group (WOG) catalog items screening/review; SNSA recommendations (including IAEA RAMP mission suggestions/recommendations).(author)

Project safety as a sustainable competitive advantage.

Science.gov (United States)

Rechenthin, David

2004-01-01

To be consistently profitable, a construction company must complete projects in scope, on schedule, and on budget. At the same time, the nature of the often high-risk work performed by construction companies can result in high accident rates. Clients and other stakeholders are placing increasing pressure on companies to decrease those accident rates. Clients routinely demand copies of safety plans and evidence of past results at the "pre-qualification" or "request for proposal" stages of the procurement process. Are high accident rates and the associated costs just a part of business? Companies that deliver on scope, schedule, and budget have a competitive advantage. Is it possible for projects with low accident rates to use it as a competitive advantage? Is the value added by safety just a temporary or parity issue, or does a successful safety program offer significant advantage to the company and the client? This article concludes that in the case of a high-risk industry, such as the construction industry, an organization with a successful safety program can promote safety performance as a sustainable competitive advantage. It is a choice the company can make.

Food Safety and Sustainable Nutrition Workshops: Educational Experiences for Primary School Children in Turin, Italy.

Science.gov (United States)

Traversa, Amaranta; Adriano, Daniela; Bellio, Alberto; Bianchi, Daniela Manila; Gallina, Silvia; Ippolito, Clara; Romano, Angelo; Durelli, Paola; Pezzana, Andrea; Decastelli, Lucia

2017-01-24

European control and prevention policies are focused to guarantee a high level of protection of consumers' health. Food-borne diseases as obesity, diabetes, food allergy, and food-borne outbreaks are increasing. To prevent food-borne diseases, it is fundamental to involve consumers, in particular children, in educational experiences aimed to learn the proper behaviours to be applied. In this context, we designed and performed 5 educational workshops about food safety, hidden allergens in food and nutrition aimed to involve children attending primary and summer school. These experiences let us collect observations about children knowledge and behaviours. From May to October 2015, a total of 1708 children aged 6 to 11 years joined our workshops. Children were involved in listening activities, laboratory experiments, handling games and sensory experiences. All participants were familiar with food allergy and were interested to know how to behave with allergic people. Children showed great curiosity in discovering that many foods normally contain live bacteria. Less than 25% of children reported to skip breakfast, to have it watching TV or to spend few minutes for it. Many of them (>75%) thought that fruits and vegetables are all year-round available and are not related to a specific period. Very few participants (food safety and nutrition educational experiences have the opportunity to increase their awareness about the correct behaviours to prevent food-borne diseases and to improve their own critical thinking about food consumption.

SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

International Nuclear Information System (INIS)

GERBER MS

2007-01-01

This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site

Education and Training in Radiation, Transport and Waste Safety Newsletter, No. 4, August 2014

International Nuclear Information System (INIS)

2014-08-01

IAEA’s Division of Radiation, Transport and Waste Safety is assisting Member States to develop national strategies for education and training in radiation, transport and waste safety via the regional projects on “Strengthening Education and Training Infrastructure, and Building Competence in Radiation Safety” (RAF/9/04, RAS/9/066, RER/9/109 and RLA/9/070). The regional workshops conducted in 2012 in this area and the results achieved were presented in the previous issues of this newsletter focussing specifically on each region of the Technical Cooperation Programme (Africa, Asia and the Pacific, Europe and Latin America). In the course of 2013, a new cycle of Regional Workshops was conducted. The workshops held in the regions of Africa, Asia and the Pacific, and Europe mainly focussed on Sharing Experience and Progress made in establishing a National Strategy for Education and Training in Radiation, Transport and Waste Safety (pages 2-5). The workshop held in the region of Latin America mainly focussed on Developing and Implementing Education and Training programmes. An overview on the results achieved by participating Member States for the period 2012-2013 is provided

Light water reactor safety research project

International Nuclear Information System (INIS)

Markoczy, G.; Aksan, S.N.; Behringer, K.; Prodan, M.; Stierli, F.; Ullrich, G.

1980-07-01

The research and development activities for the safety of Light Water Power Reactors carried out 1979 at the Swiss Federal Institute for Reactor Research are described. Considerations concerning the necessity, objectives and size of the Safety Research Project are presented, followed by a detailed discussion of the activities in the five tasks of the program, covering fracture mechanics and nondestructive testing, thermal-hydraulics, reactor noise analysis and pressure vessel steel surveillance. (Auth.)

Practice and innovation on safety management of Haiyang Nuclear Power Project

International Nuclear Information System (INIS)

Wei Guohu

2011-01-01

From the perspective of owner, this article has introduced the safety management model and practice of Haiyang Nuclear Power Project, one of AP1000 Self-reliance Program supporting projects of China. And the article has summarized characteristics of the safety management of Haiyang Project for reference and communication with nuclear or other projects. (author)

Safety technology: Emergency equipment and sea rescue techniques

Energy Technology Data Exchange (ETDEWEB)

1986-06-01

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

Cleanroom Energy Efficiency Workshop Proceedings

Energy Technology Data Exchange (ETDEWEB)

Tschudi, Bill

1999-03-15

On March 15, 1999, Lawrence Berkeley National Laboratory hosted a workshop focused on energy efficiency in Cleanroom facilities. The workshop was held as part of a multiyear effort sponsored by the California Institute for Energy Efficiency, and the California Energy Commission. It is part of a project that concentrates on improving energy efficiency in Laboratory type facilities including cleanrooms. The project targets the broad market of laboratory and cleanroom facilities, and thus cross-cuts many different industries and institutions. This workshop was intended to raise awareness by sharing case study success stories, providing a forum for industry networking on energy issues, contributing LBNL expertise in research to date, determining barriers to implementation and possible solutions, and soliciting input for further research.

Accelerator reliability workshop

International Nuclear Information System (INIS)

Hardy, L.; Duru, Ph.; Koch, J.M.; Revol, J.L.; Van Vaerenbergh, P.; Volpe, A.M.; Clugnet, K.; Dely, A.; Goodhew, D.

2002-01-01

About 80 experts attended this workshop, which brought together all accelerator communities: accelerator driven systems, X-ray sources, medical and industrial accelerators, spallation sources projects (American and European), nuclear physics, etc. With newly proposed accelerator applications such as nuclear waste transmutation, replacement of nuclear power plants and others. Reliability has now become a number one priority for accelerator designers. Every part of an accelerator facility from cryogenic systems to data storage via RF systems are concerned by reliability. This aspect is now taken into account in the design/budget phase, especially for projects whose goal is to reach no more than 10 interruptions per year. This document gathers the slides but not the proceedings of the workshop

Accelerator reliability workshop

Energy Technology Data Exchange (ETDEWEB)

Hardy, L; Duru, Ph; Koch, J M; Revol, J L; Van Vaerenbergh, P; Volpe, A M; Clugnet, K; Dely, A; Goodhew, D

2002-07-01

About 80 experts attended this workshop, which brought together all accelerator communities: accelerator driven systems, X-ray sources, medical and industrial accelerators, spallation sources projects (American and European), nuclear physics, etc. With newly proposed accelerator applications such as nuclear waste transmutation, replacement of nuclear power plants and others. Reliability has now become a number one priority for accelerator designers. Every part of an accelerator facility from cryogenic systems to data storage via RF systems are concerned by reliability. This aspect is now taken into account in the design/budget phase, especially for projects whose goal is to reach no more than 10 interruptions per year. This document gathers the slides but not the proceedings of the workshop.

Overview of DOE/ONS criticality safety projects

International Nuclear Information System (INIS)

Barber, R.W.; Brown, B.P.; Hopper, C.M.

1985-01-01

The evolution of Federal involvement with nuclear criticality safety has traversed through the 1940's and early 1950's with the Manhattan Engineering District, the 1950's and 1960's with the Atomic Energy Commission, the early 1970's with the Energy Research and Development Administration, and the late 1970's to date with the US Department of Energy. The importance of nuclear criticality safety has been maintained throughout these periods; however, criticality safety has received shifting emphases in research/applications, promulgations of regulations/standards, origins of fiscal support and organization. In June 1981 the Office of Nuclear Safety was established in response to a Department of Energy study of the impact of the March 1979 Three Mile Island accident. The organizational structure of the ONS, its program for establishing and maintaining a progressive nuclear criticality safety program, and associated projects, and current history of ONS's fiscal support of program projects is presented. With the establishment of the ONS came concomitant missions to develop and maintain nuclear safety policy and requirements, to provide independent assurance that nuclear operations are performed safely, to provide resources and management for DOE responses to nuclear accidents, and to provide technical support. In the past four years, ONS has developed and initiated a continuing Department Nuclear Criticality Safety Program in such areas as communications and information, physics of criticality, knowledge of factors affecting criticality, and computational capability

Report of the Orientation Workshop

DEFF Research Database (Denmark)

Nunez, Heilyn Camacho; Buus, Lillian; Ogange, Betty

2014-01-01

This Orientation Workshops is part of MAAGART project. The workshop is divided in three parts: 1) pre-Orientation Workshop stage, 2) Face-to-Face stage and 3) post-Orientation stage. Pre and post stages will be developed online. All the activities will take place in a virtual learning environment...... created for this purpose. Participants will receive all the information about how to access the virtual learning environment (Moodle) prior to the pre-orientation workshop. In this report we cover only the two first stages. Jørgen Bang, as a part of the Community of Practice activity, will be facilitating...

SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

Energy Technology Data Exchange (ETDEWEB)

GERBER MS

2007-12-05

This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site.

2007 Lunar Regolith Simulant Workshop Overview

Science.gov (United States)

McLemore, Carole A.; Fikes, John C.; Howell, Joe T.

2007-01-01

The National Aeronautics and Space Administration (NASA) vision has as a cornerstone, the establishment of an Outpost on the Moon. This Lunar Outpost will eventually provide the necessary planning, technology development, and training for a manned mission to Mars in the future. As part of the overall activity, NASA is conducting Earth-based research and advancing technologies to a Technology Readiness Level (TRL) 6 maturity under the Exploration Technology Development Program that will be incorporated into the Constellation Project as well as other projects. All aspects of the Lunar environment, including the Lunar regolith and its properties, are important in understanding the long-term impacts to hardware, scientific instruments, and humans prior to returning to the Moon and living on the Moon. With the goal of reducing risk to humans and hardware and increasing mission success on the Lunar surface, it is vital that terrestrial investigations including both development and verification testing have access to Lunar-like environments. The Marshall Space Flight Center (MSFC) is supporting this endeavor by developing, characterizing, and producing Lunar simulants in addition to analyzing existing simulants for appropriate applications. A Lunar Regolith Simulant Workshop was conducted by MSFC in Huntsville, Alabama, in October 2007. The purpose of the Workshop was to bring together simulant developers, simulant users, and program and project managers from ETDP and Constellation with the goals of understanding users' simulant needs and their applications. A status of current simulant developments such as the JSC-1A (Mare Type Simulant) and the NASA/U.S. Geological Survey Lunar Highlands-Type Pilot Simulant (NU-LHT-1 M) was provided. The method for evaluating simulants, performed via Figures of Merit (FoMs) algorithms, was presented and a demonstration was provided. The four FoM properties currently being assessed are: size, shape, density, and composition. Some of the

76 FR 77981 - Build-A-Bear Workshop, Inc., Provisional Acceptance of a Settlement Agreement and Order

Science.gov (United States)

2011-12-15

... CONSUMER PRODUCT SAFETY COMMISSION [CPSC Docket No. 12-C0004] Build-A-Bear Workshop, Inc... 1118.20(e). Published below is a provisionally-accepted Settlement Agreement with Build-A-Bear Workshop..., Build-A-Bear Workshop, Inc. (``Build-A-Bear'') and staff of the United States Consumer Product Safety...

ALARA issues arising for safety and security of radiation sources and security screening devices - Summary and recommendations of the 12. European ALARA network workshop

International Nuclear Information System (INIS)

Shaw, P.; Crouail, P.; Drouet, F.

2010-01-01

The 12. European ALARA Network (EAN) workshop on 'ALARA issues arising for safety and security of radiation sources and security screening devices' took place in Vienna (Austria) in October 2009. The aim of that workshop was to consider how the implementation of ALARA3, in terms of planned and emergency situations, involving worker and public doses, is affected by the introduction of security-related measures. In the case of new equipment and procedures, there was also the question of whether exposures arising from security screening devices can be justified and optimised. This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. During their discussions, the working groups identified recommendations dealing with the following topics: the implementation of the Code of Conduct and HASS4 - ensuring ALARA; balancing security and safety - how to achieve an optimum solution; the management of an emergency exposure situation from an ALARA perspective; the justification and optimisation of the use of security devices. The objective of this paper is to present the main conclusions and recommendations produced during the workshop. Individual presentations (papers and slides) as well as the reports from the working groups are available to download on the EAN web site (http://www.eu-alara.net). (authors)

Infrastructure design & road safety : OECD Workshop B3 (Infrastructure design and road safety) for CEE's and NIS held on 15th-18th November 1994, Prague (Czech Republic). Part 2: Lectures.

NARCIS (Netherlands)

2012-01-01

The workshop 'Infrastructure design and road safety ' was one of the initiatives which the OECO Steering Committee for Road Transport Research developed with the aim of exchanging information in the road transport sector, in order to respond to the urgent needs expressed by Central and Eastern

Safety Culture in New Build Projects

International Nuclear Information System (INIS)

Reiman, T.

2016-01-01

The concept of culture emphasises the social factors that have an effect on the way hazards are perceived, risks are evaluated, risk management is conducted, the current safety level is interpreted, and what is considered normal and what abnormal. It also contributes to defining the correct ways to behave in situations and correct ways to talk about safety, risks or uncertainty. Culture is something the company has created for itself that then has an effect on the company. This effect is not necessarily perceived by the company itself, since the members of the organization consider all things that happen according to their cultural taken-for-granted assumptions (“business as usual”). Thus, safety culture can either hinder or advance nuclear safety. This depends on what the shared values and assumptions are, and how they are in line with, and influence, the organizational structures, practices, personnel and technology. Safety culture requires constant and systematic development, monitoring and review during the entire life-cycle of a nuclear facility. The pre-operational phase sets many unique requirements for nuclear safety culture. For example, some of the organizations and individuals involved in the project may have no insight on how safety culture relates to nuclear power plants. Companies that work in the conventional industry typically associate safety with occupational safety issues, not with nuclear safety. Further, it may be unclear how the construction phase affects nuclear safety of an operating plant. When workers are asked to perform their work differently than previously (e.g., in conventional construction sites), explanation has to be given. For example, structures, systems and components may have different functions during emergency that exceed or differ from their quality requirements during normal operation. The strict quality requirements and use of certain methods and procedures, documentation requirements, etc., may seem unimportant if

Analysis of differences in fuel safety criteria for WWER and western PWR nuclear power plants

International Nuclear Information System (INIS)

2003-11-01

focuses on the issues of importance for the review of fuel safety cases. This report makes frequent reference to three reports which constitute the background for the workshops, two by the IAEA and one by the NEA/CSNI, these three reports have been included on a CD ROM that complements this report. The workshops were organized under the IAEA regional Technical Co-operation Project on Licensing Fuel and Fuel Modelling Codes for WWER Reactors

Final workshop proceedings of the collaborative project ''Crystalline ROCK retention processes''

Energy Technology Data Exchange (ETDEWEB)

Rabung, Thomas; Garcia, David; Montoya Vanessa; Molinero, Jorge (eds.)

2014-07-01

The present document is the proceedings of the Final Workshop of the EURATOM FP7 Collaborative Project CROCK (Crystalline Rock Retention Processes). The key driver for initiation the CP CROCK, identified by national Waste Management Organizations, is the undesired high uncertainty and the associated conservatism with respect to the radionuclide transport in the crystalline host-rock far-field around geological disposal of high-level radioactive wastes.

Background Document for Workshop no.3 of Forest Carbon Management Workshop Series

International Nuclear Information System (INIS)

Griss, P.

2002-01-01

Pollution Probe has organized a series of workshops on forest carbon management (FCM) in Canada in order to examine the opportunities, policies and infrastructure for Canada. This report summarizes the events of the third workshop which explored the verification of carbon stocks in forests. It also incorporates the results of the first 2 workshops. There are substantial opportunities for greenhouse gas (GHG) emitters to obtain carbon credits through FCM. Canada, a proponent for the eligibility of FCM under the Kyoto Protocol, must develop these opportunities domestically although policies and infrastructure needed to support FCM activities are not yet clearly identified. The Kyoto Protocol allows developed countries to use international emissions trading to help meet emissions commitments. Details for emissions trading in Canada are still being negotiated and an effective forest-based methodology for carbon dioxide equivalent credit creation must be developed. This paper reviewed the role of forests in creating or canceling out removal units (RMUs) in deforestation, afforestation, reforestation, and forest management. From an FCM perspective, buyers of carbon credits have several choices in the development of their offset portfolio, including: (1) energy type versus carbon sinks, (2) forest sinks versus agricultural/soil sinks, (3) domestic projects versus international projects, and (4) Joint Implementation projects in developed countries versus Clean Development Mechanism projects in developing countries. tabs., figs., appendices

Workshop on ethical issues and justification for high-dose budget-limited procedures: A report from an exploratory and consensus meeting held at Hairmyres Hospital, Scotland

International Nuclear Information System (INIS)

Corbett, R. H.; Malone, J.

2009-01-01

This summary report presents aspects of work that was carried out as part of the European Commission SENTINEL Project (Safety and Efficacy for New Techniques and Imaging using New Equipment to Support European Legislation). It arises from the discussions at a workshop organised by the first author at Hairmyres Hospital, East Kilbride in September 2006. The second author facilitated the workshop and moderated the discussion. The paper notes key points from the discussion and provides some pertinent comments. (authors)

Sixth international wind-diesel workshop

International Nuclear Information System (INIS)

1992-01-01

At a workshop on hybrid wind/diesel power generation systems, papers were presented on international research programs, demonstration projects, wind/diesel deployment strategies and requirements, wind/diesel market development and economics, wind turbine design requirements, and wind/diesel models and analytical tools. Separate abstracts have been prepared for 11 papers from this workshop

Sixth international wind-diesel workshop

Energy Technology Data Exchange (ETDEWEB)

1992-01-01

At a workshop on hybrid wind/diesel power generation systems, papers were presented on international research programs, demonstration projects, wind/diesel deployment strategies and requirements, wind/diesel market development and economics, wind turbine design requirements, and wind/diesel models and analytical tools. Separate abstracts have been prepared for 11 papers from this workshop.

SNF fuel retrieval sub project safety analysis document

International Nuclear Information System (INIS)

BERGMANN, D.W.

1999-01-01

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed

SNF fuel retrieval sub project safety analysis document

Energy Technology Data Exchange (ETDEWEB)

BERGMANN, D.W.

1999-02-24

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

Proceedings of the 2nd workshop on information management

International Nuclear Information System (INIS)

Hoepfner, K.A.

1992-03-01

As a practical result of this workshop it is expected that the possibilities for the acquisition of information become more transparent. From the point of view of the authorities this would be of special interest in the field of safety evaluations, on the regulatory level, and for the work of the press and public relations. The wish has been fulfilled to invite to this workshop the information experts competent in the specialist area. This means that at the end of this workshop a qualified survey over existing information sources will be available. All this is of vital importance for effective information management of the topic areas of nuclear safety, radiation protection and environmental protection. (orig./DG)

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

Food safety and sustainable nutrition workshops: educational experiences for primary school children in Turin, Italy

Directory of Open Access Journals (Sweden)

Amaranta Traversa

2017-01-01

Full Text Available European control and prevention policies are focused to guarantee a high level of protection of consumers’ health. Foodborne diseases as obesity, diabetes, food allergy, and food-borne outbreaks are increasing. To prevent food-borne diseases, it is fundamental to involve consumers, in particular children, in educational experiences aimed to learn the proper behaviours to be applied. In this context, we designed and performed 5 educational workshops about food safety, hidden allergens in food and nutrition aimed to involve children attending primary and summer school. These experiences let us collect observations about children knowledge and behaviours. From May to October 2015, a total of 1708 children aged 6 to 11 years joined our workshops. Children were involved in listening activities, laboratory experiments, handling games and sensory experiences. All participants were familiar with food allergy and were interested to know how to behave with allergic people. Children showed great curiosity in discovering that many foods normally contain live bacteria. Less than 25% of children reported to skip breakfast, to have it watching TV or to spend few minutes for it. Many of them (>75% thought that fruits and vegetables are all year-round available and are not related to a specific period. Very few participants (<25% knew that freezing is the treatment to be applied to make fresh fish safe from parasites. Children involved in food safety and nutrition educational experiences have the opportunity to increase their awareness about the correct behaviours to prevent food-borne diseases and to improve their own critical thinking about food consumption.

Physics beyond Colliders Kickoff Workshop

CERN Document Server

2016-01-01

The aim of the workshop is to explore the opportunities offered by the CERN accelerator complex and infrastructure to get new insights into some of today's outstanding questions in particle physics through projects complementary to high-energy colliders and other initiatives in the world. The focus is on fundamental physics questions that are similar in spirit to those addressed by high-energy colliders, but that may require different types of experiments. The kickoff workshop is intended to stimulate new ideas for such projects, for which we encourage the submission of abstracts.

Workshop on Physics Beyond Colliders

CERN Document Server

2016-01-01

The aim of the workshop is to explore the opportunities offered by the CERN accelerator complex and infrastructure to get new insights into some of today's outstanding questions in particle physics through projects complementary to high-energy colliders and other initiatives in the world. The focus is on fundamental physics questions that are similar in spirit to those addressed by high-energy colliders, but that may require different types of experiments. The kick-off workshop is intended to stimulate new ideas for such projects, for which we encourage the submission of abstracts.

The Preservation of Records, Knowledge and Memory (RK and M) Across Generations: Improving Our Understanding. RK and M Workshop Proceedings

International Nuclear Information System (INIS)

Gordon-Smith, Helen; Pescatore, Claudio; Schroeder, Jantine

2013-01-01

The Second Preservation of Records, Knowledge and Memory Across Generations Workshop was held 12-13 October 2012 in Issy-les-Moulineaux, France, as part of the homonymous project under the aegis of the NEA Radioactive Waste Management Committee. There were 50 participants from 11 countries representing national governments, universities, waste management agencies, safety authorities, community groups, and specialists in both the technical and social sciences. Three international organisations were also represented. The overarching goal of the workshop was to improve our understanding of the questions pertaining to the project, and the wider culture of RK and M preservation. The workshop encouraged the discussion of experience and research from project members, the wider field of radioactive waste management, and beyond that field into academia, archiving, art, and others. The underlying assumptions of the project were reconsidered and the availability of different mechanisms and models for RK and M preservation were discussed. The fundamental need for social engagement with RK and M Preservation ran through all of the themes discussed. On the first day there were three themes - 'Why Preserve RK and M', 'Conceptualising RK and M Loss', and 'How to Preserve RK and M'. 'Why Preserve RK and M' looked at the 'safety story' from the perspective of regulation, monitoring and the role of safeguards. 'Conceptualising RK and M Loss' looked at loss and recovery and 'How to Preserve RK and M' looked at mechanisms for RK and M recovery in the short and medium term. There was also a project update on the progress of the bibliography analysis. On day two, the theme of 'How to Preserve RK and M' continued, looking at the medium and long term, archives, and the pragmatic organisation of an RK and M programme. 'What to Preserve' considered the minimal set of records which should be preserved. The presentations included ongoing project studies, questionnaire analysis, academic

Distance Learning Engineering Students Languish under Project-Based Learning, but Thrive in Case Studies and Practical Workshops

Science.gov (United States)

Swart, Arthur James

2016-01-01

The International Engineering Alliance lists 12 important graduate attributes that students must demonstrate during their higher educational career. One of these important graduate attributes is the ability to solve problems, which can be demonstrated by the use of project-based learning, case studies, and practical workshops. The purpose of this…

Spent Fuel Dissolution and Source Term Modelling in Safety Assessment. Report from a Workshop at Sigtunahoejden Hotel and Conference, Sigtuna, Sweden May 17-19, 2006. Synthesis and extended abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-05-15

This report describes a workshop that was organised by the Swedish Nuclear Power Inspectorate (SKI) for assessment of the handling of near-field radionuclide retention processes by the Swedish Nuclear Fuel and Waste Management Company (SKB). The general objective with this type of meeting is to improve the knowledge and awareness of recent developments and to provide preliminary review comments. A number of SKB reports provided the general background for the workshop discussions. One report addresses the release of radionuclides from spent fuel, another the concentration limits related to radionuclide solubility and a third buffer radionuclide sorption and migration parameters. These reports comprise a basis for the handling of the spent fuel, solubility and sorption processes in new complete safety assessment SR-Can. The discussion and analysis of these background reports at the workshop therefore provide an essential element of preparation for the planned review of SR-Can. The review comments provided in this report are nonetheless of a preliminary character since the SR-Can report was not available at the time of the workshop and details about the incorporation of various potential safety features into the entirety of safety assessment were not known. The present report sets out the detailed objectives and format of the workshop in Section 2. Section 3 provides a high-level overview of processes that need to be taken into account. In Section 4, there is a brief discussion about the chemical and physical environment near the engineered barriers. Section 5 gives a more detailed description of spent fuel processes that affect the radionuclide releases. In Section 6, the key issues for radionuclide chemistry and the estimation of concentration limits for various radionuclides are discussed. Section 7 discusses radionuclide sorption and migration in the buffer and Section 8 presents overall conclusions from the workshop.

Spent Fuel Dissolution and Source Term Modelling in Safety Assessment. Report from a Workshop at Sigtunahoejden Hotel and Conference, Sigtuna, Sweden May 17-19, 2006. Synthesis and extended abstracts

International Nuclear Information System (INIS)

2007-05-01

This report describes a workshop that was organised by the Swedish Nuclear Power Inspectorate (SKI) for assessment of the handling of near-field radionuclide retention processes by the Swedish Nuclear Fuel and Waste Management Company (SKB). The general objective with this type of meeting is to improve the knowledge and awareness of recent developments and to provide preliminary review comments. A number of SKB reports provided the general background for the workshop discussions. One report addresses the release of radionuclides from spent fuel, another the concentration limits related to radionuclide solubility and a third buffer radionuclide sorption and migration parameters. These reports comprise a basis for the handling of the spent fuel, solubility and sorption processes in new complete safety assessment SR-Can. The discussion and analysis of these background reports at the workshop therefore provide an essential element of preparation for the planned review of SR-Can. The review comments provided in this report are nonetheless of a preliminary character since the SR-Can report was not available at the time of the workshop and details about the incorporation of various potential safety features into the entirety of safety assessment were not known. The present report sets out the detailed objectives and format of the workshop in Section 2. Section 3 provides a high-level overview of processes that need to be taken into account. In Section 4, there is a brief discussion about the chemical and physical environment near the engineered barriers. Section 5 gives a more detailed description of spent fuel processes that affect the radionuclide releases. In Section 6, the key issues for radionuclide chemistry and the estimation of concentration limits for various radionuclides are discussed. Section 7 discusses radionuclide sorption and migration in the buffer and Section 8 presents overall conclusions from the workshop

Workshop on Accelerator Operation (WAO 2001)

International Nuclear Information System (INIS)

Bailey, R.

2001-01-01

The 3rd Workshop on Accelerator Operation (WAO 2001) followed earlier workshops in 1996 and 1998. Most topics relevant for the efficient and effective operation of accelerators were covered. These included the tools and utilities necessary in the control rooms; the organization of accelerator operation (process monitoring, shift work, stress); the monitoring of beam quality; safety issues and standards; and questions particularly relevant for superconducting accelerators, in particular cryogenics. (author)

First Workshop on Design and Construction of Deep Repositories - Theme: Excavation through water-conducting major fracture zones

International Nuclear Information System (INIS)

Baeckblom, G.; Svemar, C.

1994-01-01

Final disposal of high-level nuclear waste has not yet been carried out in any country today. The concepts under development are all based on geological repositories, i.e., disposal at a sufficient depth below the surface to provide stable mechanical, hydrological and chemical conditions during the period the waste needs to be isolated from man. In the cases where crystalline bedrock is considered the proposed repository depths vary between 300-1000 m. The construction, operation and sealing of a deep geological repository must meet various criteria that in many respects are more detailed and more demanding than usual in underground construction projects today. The work shall be done so that occupational safety is ensured. The work also shall conform to whatever restrictions are necessary for ensuring pre-closure operational safety and post-closure long-term safety. March 1993 SKB arranged a two-day international workshop to discuss design and construction of repositories. Close to 40 participants from eight countries shared experiences regarding passage of major water-conducting fracture zones and other matters. This report summarizes the contributions to the workshop

Nuclear Safety Project. Annual report 1986

International Nuclear Information System (INIS)

1987-09-01

The annual report 1986 is a detailed description of work within the Nuclear Safety Project performed in 1986 in the nuclear safety field by KfK institutes and departments and by external institutes on behalf of KfK. It includes individual research activities on dynamic loads and strains of reactor components under accident conditions, fuel behaviour under accident conditions, investigation and control of LWR core-meltdown accidents, improvement of fission product retention and reduction of radiation exposure, and on behaviour, impact and removal of released pollutants. (DG)

TPC workshop summary

International Nuclear Information System (INIS)

Nygren, D.R.

1984-01-01

The Time Projection Chamber (TPC) concept is now nearly ten years old and, as is evident in this workshop, is still evolving in many directions. From the liquid xenon TPC for double beta decay studies to the impressively large second generation TPC for the LEP experiment ALEPH, the surprising diversity of current applications is apparent. This workshop, the first to concentrate solely on the TPC has provided a most congenial and rewarding occasion for all TPC enthusiasts to share experience, results, and ideas

25 CFR 170.144 - What are eligible highway safety projects?

Science.gov (United States)

2010-04-01

... RESERVATION ROADS PROGRAM Indian Reservation Roads Program Policy and Eligibility Highway Safety Functions... management system; (g) Education and outreach highway safety programs, such as use of child safety seats... 25 Indians 1 2010-04-01 2010-04-01 false What are eligible highway safety projects? 170.144...

Annual colloquium 1976 of the project nuclear safety

International Nuclear Information System (INIS)

1976-11-01

The present report gives the full text of the nine papers read during the annual colloquium 1976 of the Project Nuclear Safety at Karlsruhe Nuclear Research Centre, in which the main activities and findings of the project in 1976 are contained. (RW) [de

Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

Science.gov (United States)

Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

2013-12-01

This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

Report on the final BRACElet workshop

Directory of Open Access Journals (Sweden)

Tony Clear

Full Text Available This paper reports on the thirteenth and final BRACElet workshop. In this paper we provide a brief retrospective review of the workshops and the findings that have resulted from this multi-institutional multinational investigation into the teaching and learning of novice programmers. Subsequently we report on the work undertaken during the final workshop and then discuss future avenues for research that have evolved as a result of the BRACElet project.

Expediting Clinician Adoption of Safety Practices: The UCSF Venous Access Patient Safety Interdisciplinary Education Project

National Research Council Canada - National Science Library

Donaldson, Nancy E; Plank, Rosemary K; Williamson, Ann; Pearl, Jeffrey; Kellogg, Jerry; Ryder, Marcia

2005-01-01

...) Venous Access Device (VAD) Patient Safety Interdisciplinary Education Project was to develop a 30-hour/one clinical academic unit VAD patient safety course with the aim of expediting clinician adoption of critical concepts...

Software qualification for digital safety system in KNICS project

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Lee, Dong-Young; Choi, Jong-Gyun

2012-01-01

In order to achieve technical self-reliance in the area of nuclear instrumentation and control, the Korea Nuclear Instrumentation and Control System (KNICS) project had been running for seven years from 2001. The safety-grade Programmable Logic Controller (PLC) and the digital safety system were developed by KNICS project. All the software of the PLC and digital safety system were developed and verified following the software development life cycle Verification and Validation (V and V) procedure. The main activities of the V and V process are preparation of software planning documentations, verification of the Software Requirement Specification (SRS), Software Design Specification (SDS) and codes, and a testing of the software components, the integrated software, and the integrated system. In addition, a software safety analysis and a software configuration management are included in the activities. For the software safety analysis at the SRS and SDS phases, the software Hazard Operability (HAZOP) was performed and then the software fault tree analysis was applied. The software fault tree analysis was applied to a part of software module with some critical defects identified by the software HAZOP in SDS phase. The software configuration management was performed using the in-house tool developed in the KNICS project. (author)

Deciphering the Colon Cancer Genes-Report of the InSiGHT-Human Variome Project Workshop, UNESCO, Paris 2010

NARCIS (Netherlands)

Kohonen-Corish, Maija R. J.; Macrae, Finlay; Genuardi, Maurizio; Aretz, Stefan; Bapat, Bharati; Bernstein, Inge T.; Burn, John; Cotton, Richard G. H.; den Dunnen, Johan T.; Frebourg, Thierry; Greenblatt, Marc S.; Hofstra, Robert; Holinski-Feder, Elke; Lappalainen, Ilkka; Lindblom, Annika; Maglott, Donna; Moller, Pal; Morreau, Hans; Moeslein, Gabriela; Sijmons, Rolf; Spurdle, Amanda B.; Tavtigian, Sean; Tops, Carli M. J.; Weber, Thomas K.; de Wind, Niels; Woods, Michael O.

The Human Variome Project (HVP) has established a pilot program with the International Society for Gastrointestinal Hereditary Tumours (InSiGHT) to compile all inherited variation affecting colon cancer susceptibility genes. An HVP-InSiGHT Workshop was held on May 10, 2010, prior to the HVP

Workshop on Developing Safe Software

International Nuclear Information System (INIS)

Lawrence, J.D.

1994-11-01

The Workshop on Developing Safe Software was held July 22--23, 1992, at the Hotel del Coronado, San Diego, California. The purpose of the workshop was to have four world experts discuss among themselves software safety issues which are of interest to the US Nuclear Regulatory Commission. These issues concern the development of software systems for use in nuclear power plant protection systems. The workshop comprised four sessions. Wednesday morning, July 22, consisted of presentations from each of the four panel members. On Wednesday afternoon, the panel members went through a list of possible software development techniques and commented on them. The Thursday morning, July 23, session consisted of an extended discussion among the panel members and the observers from the NRC. A final session on Thursday afternoon consisted of a discussion among the NRC observers as to what was learned from the workshop

Workshop on developing safe software

International Nuclear Information System (INIS)

Lawrence, J.D.

1992-01-01

The Workshop on Developing Safe Software was held July 22--23 at the Hotel del Coronado, San Diego, California. The purpose of the workshop was to have four world experts discuss among themselves software safety issues which are of interest to the U. S. Nuclear Regulatory Commission (NRC). These issues concern the development of software systems for use in nuclear power plant protection systems. The workshop comprised four sessions. Wednesday morning, July 22, consisted of presentations from each of the four panel members. On Wednesday afternoon, the panel members went through a list of possible software development techniques and commented on them. The Thursday morning, July 23, session consisted of an extended discussion among the panel members and the observers from the NRC. A final session on Thursday afternoon consisted of a discussion among the NRC observers as to what was teamed from the workshop

Virtual Workshop

DEFF Research Database (Denmark)

Buus, Lillian; Bygholm, Ann

In relation to the Tutor course in the Mediterranean Virtual University (MVU) project, a virtual workshop “Getting experiences with different synchronous communication media, collaboration, and group work” was held with all partner institutions in January 2006. More than 25 key-tutors within MVU...

A series of student design projects for improving and modernizing safety helmets

NARCIS (Netherlands)

Beurden, van K.M.M. (Karin); Boer, de J. (Johannes); Stilma, M. (Margot); Teeuw, W.B. (Wouter)

2014-01-01

The Saxion Research Centre for Design and Technology employs many students during research projects. This paper discusses a series of student design projects on safety helmets in the Safety@Work project. At construction sites workers are required to wear personal protective equipment during their

Computer-Assisted Language Learning : proceedings of the seventh Twente Workshop on Language Technology

NARCIS (Netherlands)

Appelo, L.; de Jong, Franciska M.G.

1994-01-01

TWLT is an acronym of Twente Workshop(s) on Language Technology. These workshops on natural language theory and technology are organised bij Project Parlevink (sometimes with the help of others) a language theory and technology project conducted at the Department of Computer Science of the

4"t"h Annual workshop proceedings of the collaborative project ''Redox phenomena controlling systems'' (7"t"h EC FP CP RECOSY)

International Nuclear Information System (INIS)

Altmaier, Marcus; Kienzler, Bernhard; Duro, Lara; Grive, Mireia; Montoya, Vanessa

2012-01-01

The EURATOM 7"t"h EC Framework Program Collaborative Project REdox phenomena Controlling SYstems (RECOSY) started in April 2008 and extends over 4 years. Although redox is not a new geochemical issue, different questions are still not resolved. For this reason, main objectives of RECOSY project are a) the sound understanding of redox phenomena controlling the long-term release/retention of radionuclides in nuclear waste disposal, b) providing tools to apply the result to Performance Assessment/Safety Case, c) training of next generation and d) documentation and communication of the results. To this aim, the project set up a consortium of 32 Beneficiaries/Contractors and 6 Associated Groups. The consortium includes key European Research Institutes, Universities, National Waste Management Agencies and SMEs, from 13 EURATOM signatory states, Russia, Japan, Korea, USA and one European Joint Research Centre. The ReCosy concept is innovative in the scientific approach to the redox phenomena. It includes i) advanced analytical tools, ii) investigations of processes responsible for redox control (thermodynamically and kinetically controlled processes, surface reactions and microbial processes,..), iii) provision of required data on redox controlling processes, and iv) response to disturbances in disposal systems. The work program is structured along six RTD workpackages (WP1-6). They cover near-field and far field aspects as well as all relevant host-rocks considered in Europe. In WP1, the scientific state-of-the-art and its application to Performance Assessment/Safety Case is documented and regularly updated. WP2 focuses on development of redox determination methods. WP3 focuses on redox response of defined and near-natural systems. WP4 studies the redox reactions of radionuclides. WP5 focuses on Redox processes in radionuclide transport and WP6 deals with redox reactions affecting the spent fuel source-term. Specific workpackages on knowledge management, education and

Third Joint GIF–IAEA Workshop on Safety Design Criteria for Sodium-Cooled Fast Reactors, 26-27 February 2013, Vienna, Austria. Summary Report

International Nuclear Information System (INIS)

2013-01-01

The main objectives of the meeting were to: • Present and share information on the work carried out by GIF, the IAEA and the Member States on the definition of safety design criteria for SFR, including safety approach and requirements on general plant design; • Present the document prepared by the GIF-SFR Task Force on Safety Design Criteria; • Present and discuss safety design concepts of SFRs under development in Member States, with particular emphasis on design measures against Design Basis Accidents and Design Extended Conditions, as well as the associated safety evaluations and supporting R&D; • Draft a room document which should be the basis of the discussion for the Panel on Safety Design Criteria of the FR13 Conference in Paris. • Discuss the results and agree on the future actions of the 3rd Joint GIF-IAEA Workshop on Safety of Sodium-Cooled Fast Reactors

Building Strong Geoscience Departments Through the Visiting Workshop Program

Science.gov (United States)

Ormand, C. J.; Manduca, C. A.; Macdonald, H.; Bralower, T. J.; Clemens-Knott, D.; Doser, D. I.; Feiss, P. G.; Rhodes, D. D.; Richardson, R. M.; Savina, M. E.

2011-12-01

The Building Strong Geoscience Departments project focuses on helping geoscience departments adapt and prosper in a changing and challenging environment. From 2005-2009, the project offered workshop programs on topics such as student recruitment, program assessment, preparing students for the workforce, and strengthening geoscience programs. Participants shared their departments' challenges and successes. Building on best practices and most promising strategies from these workshops and on workshop leaders' experiences, from 2009-2011 the project ran a visiting workshop program, bringing workshops to 18 individual departments. Two major strengths of the visiting workshop format are that it engages the entire department in the program, fostering a sense of shared ownership and vision, and that it focuses on each department's unique situation. Departments applied to have a visiting workshop, and the process was highly competitive. Selected departments chose from a list of topics developed through the prior workshops: curriculum and program design, program elements beyond the curriculum, recruiting students, preparing students for the workforce, and program assessment. Two of our workshop leaders worked with each department to customize and deliver the 1-2 day programs on campus. Each workshop incorporated exercises to facilitate active departmental discussions, presentations incorporating concrete examples drawn from the leaders' experience and from the collective experiences of the geoscience community, and action planning to scaffold implementation. All workshops also incorporated information on building departmental consensus and assessing departmental efforts. The Building Strong Geoscience Departments website complements the workshops with extensive examples from the geoscience community. Of the 201 participants in the visiting workshop program, 140 completed an end of workshop evaluation survey with an overall satisfaction rating of 8.8 out of a possible 10

Proceedings of the CNRA Workshop on New Reactor Siting, Licensing and Construction Experience

International Nuclear Information System (INIS)

2011-01-01

This report documents the proceedings from the 'Workshop on New Reactor Siting, Licensing and Construction Experience', held in Prague, Czech Republic on 15-17 September 2010. A total of 59 specialists from 16 countries and international organisations attended. The Meeting was sponsored by the OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities and hosted by the State Office for Nuclear Safety (SUJB) in Czech Republic. The objectives of the workshop were to review and discuss recent and past construction experience lessons learned including perspectives from regulatory authorities, as well as vendors, and licensee. The workshop addressed issues associated with project management resources including: a) overall human resources, expertise, experience and organisation available to the licensee, b) capability of each potential vendor (in-house knowledge and skills versus planned subcontracting and subcontractor management). The workshop also discussed the lessons learned in the regulation of site selection, evaluation and site preparation as well as the review of regulatory practices for the licensing of new reactors, including the regulatory body infrastructure, staffing and expertise needed. The workshop provided an excellent opportunity to communicate recent experience on these topics to a wider audience, including participants from OECD member countries as well as New Entrants from non-OECD member countries. The workshop allowed the WGRNR group to introduce and discuss the current programme of work and products under development in order to gain insights from workshop participants on each of the programme of work areas, and get feedback on additional focus areas. The workshop was structured in 4 technical sessions, each followed by ample time for panel discussions. The first technical session was devoted to presentations of the licensing process for new reactors followed by different member countries. The second technical session was

Nuclear safety research project. Annual report 1995

International Nuclear Information System (INIS)

Hueper, R.

1996-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report 1995 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1996. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

Safety of modifications at nuclear power plants - the role of minor modifications and human and organisational factors

International Nuclear Information System (INIS)

2005-01-01

Operating experience repeatedly shows that changes and modifications at nuclear power plants (NPPs) may lead to safety significant events. At the same time, modifications are necessary to ensure a safe and economic functioning of the NPPs. To ensure safety in all plant configurations it is important that modification processes are given proper attention both by the utilities and the regulators. The operability, maintainability and testability of every modification should be thoroughly assessed from different points of view to ensure that no safety problems are introduced. The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) has recently addressed the issue of modifications by organising a 'Workshop on Modifications at Nuclear Power Plants Operating Experience, Safety Significance and Role of Human Factors'. This workshop was undertaken as a joint effort of the Working Group on Operating Experience (WGOE) and the Special Experts Group on Human and Organisational Factors (SEGHOF), and it was held at the OECD Headquarters in Paris on October 6 to 8, 2003. The initiative to organise the workshop was taken by the WGOE and the SEGHOF based on findings from events and incidents due to modifications at nuclear power plants in the world and weaknesses experienced in modification processes. During the workshop, the WGOE focused on the theme of 'Minor Modifications and their Safety Significance', while the SEGHOF focused on the topic 'Human and Organisational Factors in NPP Modifications'. This report is based on material collected before the workshop, the workshop proceedings, discussions of the group of experts responsible for the arrangement of the workshop, and additional material collected by a consultant. The workshop was preceded by extensive preparations, which included collection of national surveys in response to questionnaires on modifications at the NPPs. Not all of these surveys were available at the workshop, but their findings have now been included

Technology and Components of Accelerator-driven Systems. Second International Workshop Proceedings, Nantes, France, 21-23 May 2013

International Nuclear Information System (INIS)

2015-01-01

The accelerator-driven system (ADS) is a potential transmutation system option as part of partitioning and transmutation strategies for radioactive waste in advanced nuclear fuel cycles. Following the success of the workshop series on the utilisation and reliability of the High Power Proton Accelerators (HPPA), the scope of this new workshop series on Technology and Components of Accelerator-driven Systems has been extended to cover subcritical systems as well as the use of neutron sources. The workshop organised by the OECD Nuclear Energy Agency provided experts with a forum to present and discuss state-of-the-art developments in the field of ADS and neutron sources. A total of 40 papers were presented during the oral and poster sessions. Four technical sessions were organised addressing ADS experiments and test facilities, accelerators, simulation, safety, data, neutron sources that were opportunity to present the status of projects like the MYRRHA facility, the MEGAPIE target, FREYA and GUINEVERE experiments, the KIPT neutron source, and the FAIR linac. These proceedings include all the papers presented at the workshop

Le Nouveau Manuel de Formation sur l'Elaboration et la Gestion des Projets. (The New Project Design and Management Workshop Training Manual).

Science.gov (United States)

Peace Corps, Washington, DC. Information Collection and Exchange Div.

A french language version of a training manual that presents guidelines for planning and conducting a project design and management (PDM) workshop to teach Peace Corps volunteers to involve local community members in the process of using participatory analysis tools and planning and implementing projects meeting local desires and needs. The first…

DNA Microarray Workshop

National Research Council Canada - National Science Library

Lauro, Bernie

1999-01-01

.... Funding for the workshop was provided by the US Department of Defense (USAMRAA). The aim of the meeting was to discuss how to best use the data derived from the Malaria Genome Sequencing Project for the functional analysis of the genome...

Radiation safety at the West Valley Demonstration Project

International Nuclear Information System (INIS)

Hoffman, R.L.

1997-01-01

This is a report on the Radiation Safety Program at the West Valley Demonstration Project (WVDP). This Program covers a number of activities that support high-level waste solidification, stabilization of facilities, and decontamination and decommissioning activities at the Project. The conduct of the Program provides confidence that all occupational radiation exposures received during operational tasks at the Project are within limits, standards, and program requirements, and are as low as reasonably achievable

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

Main benefits from 30 years of joint projects in nuclear safety

International Nuclear Information System (INIS)

Thadani, Ashok; Teschendorff, Victor; Vitanza, Carlo; Hrehor, Miroslav

2012-01-01

One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, primarily in the areas of nuclear safety and radioactive waste management, enable interested countries, on a cost-sharing basis, to pursue research or the sharing of data with respect to particular areas or issues. Over the years, more than 30 joint projects have been conducted with wide participation of member countries. The purpose of this report is to describe the achievements of the OECD/NEA joint projects on nuclear safety research that have been carried out over the past three decades, with a particular focus on thermal-hydraulics, fuel behaviour and severe accidents. It shows that the resolution of specific safety issues in these areas has greatly benefited from the joint projects' activities and results. It also highlights the added value of international co-operation for maintaining unique experimental infrastructure, preserving skills and generating new knowledge

Appalachian Stream Mitigation Workshop

Science.gov (United States)

A 5 day workshop in 2011 developed for state and federal regulatory and resource agencies, who review, comment on and/or approve compensatory mitigation plans for surface coal mining projects in Appalachia

Identification and applicability of analogues for a safety case for a HLW repository in evaporites: results from a NEA workshop

Energy Technology Data Exchange (ETDEWEB)

Noseck, U.; Wolf, J. [Gesellschaft für Anlagen und Reaktorsicherheit (GRS) mbH, Brunswick (Germany); Steininger, W. [Project Management Agency Karslruhe Water Technology and Waste Management, PTKA-WTE, Karlsruhe Institute of Technology, KIT, Eggenstein-Leopoldshafen (Germany); Miller, B. [AMEC, The Renaissance Center, Warrington (United Kingdom)

2015-06-15

A workshop was held in September 2012 in Braunschweig, Germany, to discuss the potential for natural and anthropogenic analogue studies to contribute to safety cases for radioactive waste repositories constructed in salt formations. Presentations were given on many analogue sites and systems from different countries. Discussions at the workshop then addressed the following aspects that are particularly relevant to the safety concept for radioactive waste disposal in salt: (1) the long-term integrity of rock salt formations, (2) the integrity of technical barriers, and (3) microbial, chemical and transport processes. A diverse range of natural systems were discussed as potential analogues for the integrity of rock salt. These included the deformation of anhydrite layers in rock salt; the response of rock salt to mechanical and thermal loads; and the isotopic signatures of syngenetic waters contained in fluid inclusions. Some anthropogenic examples drawn from the oil and gas industries, and from hazardous waste disposal, were proposed as analogues for the integrity of (geo)technical barriers. A broad range of studies on natural and anthropogenic salt-brine systems were identified as potential analogues for the radionuclide sorption and (co)precipitation process that may take place in the repository near and far fields, as well as for understanding the significance of hydrocarbons and microbial processes. It was evident from discussions at the workshop that there are some specific technical issues that may benefit from further analogue study, particularly the compaction of crushed salt backfill, the viability of microbes in the near-field, the stability of plugs and seals, the deformation of anhydrite, and isotope signatures in fluid inclusions. (authors)

Workshop objectives and structure

International Nuclear Information System (INIS)

2004-01-01

The overall aim of the Workshop was to create a platform in order to better understand different approaches to managing uncertainty in post-closure safety cases and regulatory approaches in different national waste management programmes. The principal objectives of the Workshop were to: - To identify common elements in different approaches for managing uncertainty. - To facilitate information exchange and to promote discussion on different technical approaches to the management and characterisation of uncertainty and on the role of risk. - To explore the merits of alternative approaches to risk-informed decision making. - To identify the potential for further developments of methods or strategies to support the management of uncertainties. The workshop was organised into plenary sessions and working group discussions: The first plenary session focused on establishing a framework for understanding the management of uncertainties and the use of risk. It comprised oral presentations drawing on a range of experience from both active participants in the development and assessment of safety cases and keynotes presentations by external participants involved in risk management in other sectors. The working group discussions covered three technical themes: Risk management and decision making. Regulatory requirements and review of uncertainty and risk in safety cases. Practical approaches and tools for the management of uncertainties and the assignment of probabilities, the use of expert judgements, and the presentation of information on uncertainties and risk were examined. The aim of the working groups was to develop an understanding of the specific issues, and to identify any further activities that will support the development and/or evaluation of safety cases. The round up plenary session brought together information and conclusions from each of the working groups. Common elements in the different approaches to treating uncertainty and risk were identified, along with

OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations - Workshop Proceedings

International Nuclear Information System (INIS)

2013-01-01

Best-Estimate Methods plus Uncertainty Evaluation are gaining increased interest in the licensing process. On the other hand, lessons learnt from the BEMUSE (NEA/CSNI/R(2011)3) and SM2A (NEA/CSNI/R(2011)3) benchmarks, progress of UAM benchmark, and answers to the WGAMA questionnaire on the Use of Best-Estimate Methodologies show that improvements of the present methods are necessary and new applications appear. The objective of this workshop is to provide a forum for a wide range of experts to exchange information in the area of best estimate analysis and uncertainty evaluation methods and address issues drawn-up from BEMUSE, UAM and SM2A activities. Both, improvement of existing methods and recent new developments are included. As a result of the workshop development, a set of recommendations, including lines for future activities were proposed. The organisation of the Workshop was divided into three parts: Opening session including key notes from OECD and IAEA representatives, Technical sessions, and a Wrap-up session. All sessions included a debate with participation from the audience constituted by 71 attendees. The workshop consisted of four technical sessions: a) Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches to deal with Best Estimate codes and uncertainties evaluations. A total of six papers were presented. One initial paper summarized the existing methods; the following open papers were focused on specific methods stressing their bases, peculiarities and advantages. As a result of the session a picture of the current State of the Art was obtained. b) International comparative activities: This session reviewed the set of international activities around the subject of BEPU methods benchmarking and development. From each of the activities a description of the objectives, development, main results, conclusions and recommendations (in case it is finalized) was presented. This

VALOIR 2012 2nd Workshop on Managing the Client Value Creation Process in Agile Projects: Message from the Chairs

NARCIS (Netherlands)

Pérez, Jennifer; Buglione, Luigi; Daneva, Maia; Dieste, Oscar; Jedlitschka, Andreas; Juristo, Natalia

2012-01-01

Welcome to the 2nd Workshop on Managing the Client Value Creation Process in Agile Projects (VALOIR) at the PROFES 2012 conference! The overall goal of VALOIR is to make the knowledge on value creation and management explicit, encouraging the discussion on the use of measurement and estimation

Radiation safety for decommissioning projects

International Nuclear Information System (INIS)

Ross, A.C.

1999-01-01

Decommissioning of redundant nuclear facilities is a growth area in the UK at the present time. NUKEM Nuclear Limited is a leading-edge nuclear decommissioning and waste management contractor (with its own in-house health physics and safety department), working for a variety of clients throughout the UK nuclear industry. NUKEM Nuclear is part of the prestigious, international NUKEM group, a world-class organization specializing in nuclear engineering and utilities technologies. NUKEM Nuclear is involved in a number of large, complex decommissioning projects, both in its own right and as part of consortia. This paper explores the challenges presented by such projects and the interfaces of contractor, client and subcontractors from the point of view of a radiation protection adviser. (author)

Summary of the GNWT Dehcho regional workshop on the social impacts of the Mackenzie Valley gas project

International Nuclear Information System (INIS)

2005-01-01

The proposed Mackenzie Gas Project will span at least 20 years and is expected to have significant social impacts. This workshop provided a forum for communities and government to evaluate the social impacts of the project, as well as a means for initiating collaborative planning to monitor and manage them over the next 20 years. Local plans for managing the impacts during the construction of the pipeline were discussed, as well as issues concerning future economic activity, demographic changes and long-lasting social impacts. Participants included government and community representatives from various areas in the Northwest Territories (NT). Impacts on employment and income were reviewed, as well as issues concerning housing, health and wellness. The role of the NT bureau of statistics in the monitoring of social trends was examined. Current government resources for managing impacts were evaluated as well as various social envelope departments. Community resources for managing social impacts were reviewed. Positive and negative impacts were discussed for each of the topics presented at the workshops, as well as current and future mitigation efforts. Participants developed concrete suggestions for monitoring impacts, assessing resource needs and collaborating. refs., tabs., figs.

A root cause analysis project in a medication safety course.

Science.gov (United States)

Schafer, Jason J

2012-08-10

To develop, implement, and evaluate team-based root cause analysis projects as part of a required medication safety course for second-year pharmacy students. Lectures, in-class activities, and out-of-class reading assignments were used to develop students' medication safety skills and introduce them to the culture of medication safety. Students applied these skills within teams by evaluating cases of medication errors using root cause analyses. Teams also developed error prevention strategies and formally presented their findings. Student performance was assessed using a medication errors evaluation rubric. Of the 211 students who completed the course, the majority performed well on root cause analysis assignments and rated them favorably on course evaluations. Medication error evaluation and prevention was successfully introduced in a medication safety course using team-based root cause analysis projects.

Proceedings of the 2010 renewable energy infrastructure workshop

International Nuclear Information System (INIS)

2010-01-01

This workshop provided a forum for electric power industry leaders and key stakeholders to discuss Canada's renewable energy infrastructure needs. The workshop was held to provide practical solutions for meeting the increased demand for renewable energy as well as to offer a range of marketplace options and funding opportunities. Participants in the workshop examined the regulatory framework of the Green Energy Act and its potential impact on organizations. Approval process procedures for renewable energy projects were reviewed, and methods of ensuring the integration of renewable energy projects with current business strategies were discussed. Communications strategies for managing the public perception of energy project were presented. Policy barriers to infrastructure development were outlined. Methods of developing partnerships with Aboriginal communities were also discussed. The conference featured 16 presentations, of which 3 have been catalogued separately for inclusion in this database. tabs., figs.

Advanced Grid Control Technologies Workshop Series | Energy Systems

Science.gov (United States)

: Smart Grid and Beyond John McDonald, Director, Technical Strategy and Policy Development, General Control Technologies Workshop Series In July 2015, NREL's energy systems integration team hosted workshops the Energy Systems Integration Facility (ESIF) and included a technology showcase featuring projects

Substantiation of the safety in the technical project of Belene NPP

International Nuclear Information System (INIS)

Boyadzhiev, A.

1990-01-01

The chapter contains an evaluation of the safety of Belene NPP project, based on an experts study of the corresponding volume of the Technical Project documentation of the main contractor and also on other related documents. The authors state that most of the remarks are constitutive, part of them requiring additional information or research. The general explicit conclusion is that the materials on the safety substantiation provided in the project are insufficient for making final statements on the safety of the NPP and there is a need for a detailed analysis and expertise. There are 12 topical conclusion paragraphs and each of them comprises a number of remarks. Among the remarks there are some related to the reactivity coefficient values in certain modes of operation, the problem of the mechanical safety and control system efficiency, the unacceptable operation at nominal power in case of stringent safety rules enforcement, the insufficiency of the PSA, the automatic control systems and the software codes not standing up to the contemporary requirements. (R.Ts.)

Scientific basis for a safety case of deep geological repositories

Energy Technology Data Exchange (ETDEWEB)

Noseck, Ulrich; Becker, Dirk-Alexander; Brasser, Thomas [and others

2012-11-15

. - The project on self-sealing backfill (SVV) ended in February 2010. However, further long-term observation work at Teutschenthal mine, where the material has been injected and tested in-situ, was performed within the project presented here. - National workshops have been performed to discuss and document the state-of-the-art of topics relevant for the safety case. Within this project a workshop on fundamental questions on the hydrogeology in sedimentary systems in Northern Germany and a workshop on sealing systems in a repository for HLW were performed. - The impact of future changes in climate on flow and transport in the geosphere as well on the exposure in the biosphere was further investigated with emphasis on the role of transitions between different discrete climate states. - With respect to natural analogues some final work has been performed at the ana-logue site in Ruprechtov, Czech Republic. The kaolin excavation at the site allowed checking on a larger scale the assumptions for the geological structure used in the conceptual model and the impact of disturbances on the uranium enrichment.

Scientific basis for a safety case of deep geological repositories

International Nuclear Information System (INIS)

Noseck, Ulrich; Becker, Dirk-Alexander; Brasser, Thomas

2012-11-01

. - The project on self-sealing backfill (SVV) ended in February 2010. However, further long-term observation work at Teutschenthal mine, where the material has been injected and tested in-situ, was performed within the project presented here. - National workshops have been performed to discuss and document the state-of-the-art of topics relevant for the safety case. Within this project a workshop on fundamental questions on the hydrogeology in sedimentary systems in Northern Germany and a workshop on sealing systems in a repository for HLW were performed. - The impact of future changes in climate on flow and transport in the geosphere as well on the exposure in the biosphere was further investigated with emphasis on the role of transitions between different discrete climate states. - With respect to natural analogues some final work has been performed at the ana-logue site in Ruprechtov, Czech Republic. The kaolin excavation at the site allowed checking on a larger scale the assumptions for the geological structure used in the conceptual model and the impact of disturbances on the uranium enrichment.

Cyanotype: Workshops for people with early dementia

OpenAIRE

Moreno Sáez, María del Carmen; Gutiérrez-Párraga, Teresa; Saavedra Macías, Francisco Javier (Coordinador); Español Nogueiro, Alicia (Coordinador); Arias Sánchez, Samuel (Coordinador); Calderón García, Marina (Coordinador)

2017-01-01

The workshop "Cyanotype: Workshops for people with early dementia", carried out at the 5th International Conference on Health Humanities introduced the cyanotype. The cyanotype is a 19th century photographic technique that the research project used as a way for preventing the decline of faculties of people living with diseases that provoke memory loss. The activities carried out in the cyanotype workshop at the Conference were based on the creation of photographic images that could be interve...

Fiscal 1999 engineer exchange project (field of coal mining technology), international exchange project. Domestic workshop; 1999 nendo gijutsusha koryu jigyo (tanko gijutsu bun'ya) kokusai koryu jigyo. Kokunai workshop

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-03-01

The domestic workshop invites Japanese engineers and engineers from coal producing countries for the exchange of coal mining technologies and aims to substantiate and facilitate the dispatching and receiving of engineers under training programs. The main subject of the Asia-Pacific coal technology workshop was 'Coal for the 21st century - resources and technology,' and there were two sessions held on September 8, titled 'Trends and tasks of coal resources exploitation' and 'Coal resources and production technology.' Lectures were delivered by five overseas and five Japanese coal engineering experts. On September 9, nine essays were presented concerning 'Coal resources and security problems' and 'Coal resources and environmental problems.' In addition, a panel discussion was held, titled 'Coal resources assessment and technology.' Importance was emphasized of the correct assessment of the magnitude of resources, development of probing technologies to collect more detailed information, improvement of digging speeds applicable to faces for large and high-efficiency mining, development of coal mining technologies for increased recovery, etc. Information was exchanged on various occasions and partnership was enhanced between the participants to the advantage of engineer exchanging projects in the future. (NEDO)

Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

Energy Technology Data Exchange (ETDEWEB)

Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

2011-06-01

The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

Report on high energy neutron dosimetry workshop

International Nuclear Information System (INIS)

Alvar, K.R.; Gavron, A.

1993-01-01

The workshop was called to assess the performance of neutron dosimetry per the responses from ten DOE accelerator facilities to an Office of Energy Research questionnaire regarding implementation of a personnel dosimetry requirement in DRAFT DOE 5480.ACC, ''Safety of Accelerator Facilities''. The goals of the workshop were to assess the state of dosimetry at high energy accelerators and if such dosimetry requires improvement, to reach consensus on how to proceed with such improvements. There were 22 attendees, from DOE Programs and contract facilities, DOE, Office of Energy Research (ER), Office of Environmental Safety and Health (EH), Office of Fusion Energy, and the DOE high energy accelerator facilities. A list of attendees and the meeting agenda are attached. Copies of the presentations are also attached

Proceedings of the National Training Workshop on Neonatal Hypothyroidism Screening

International Nuclear Information System (INIS)

Osifo, B.O.A.

2002-05-01

The National Training Workshop on Neonatal Hypothyroidism screening project was conceived in 2000 and was held at the University of Ibadan from May 5 - May 8, 2002. The National Neonatal Hypothyroidism Screening project is a Technical Cooperation Project between the International Atomic Energy Agency and the Federal Government of Nigeria. The Workshop was organized to raise the awareness to the Health related professionals and Policy makers on the importance of screening for Neonatal Hypothyroidism in our country. Neonatal Hypothyroidism is a result of lack of the thyroid hormones in the neonates and this is mostly due to iodine deficiency in our environment - both in the soil and water. This lack of thyroid hormones in the neonates if not treated leads to a serious disease known as Cretinism. Cretinism affects both the mental and physical developments of these children. This Training Workshop focussed on the importance of the Screening programme for all urgent treatment. The Workshop also showed clearly that lack of care and treatment of such neonates in Nigeria so as to identify the neonates that need urgent treatment. The Workshop also showed clearly that lack of care and treatment of such neonates would have a profound detrimental effect on the social and economical development of Nigeria. The spread of Iodine Deficiency in our country is nation wide. It is not based on political zoning system. Rather, Cretinism is a problem in our country and the participants are convinced that it can be prevented by the support of the Federal Government in the form of the provision of Transportation for the three centres in the country - Ibadan, Jos and Port-Harcourt, for collection of blood specimens and regular Counterpart Funding for this IAEA project. The organizers of this Workshop will like to express their sincere thanks to International Atomic Energy Agency who not only supplies all the equipment and reagents for this national project but also funded this National

Proceedings of the workshop on Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS)

International Nuclear Information System (INIS)

2007-01-01

Computational Fluid Dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coolant system to be better described. The Committee on the Safety of Nuclear Installations (CSNI), which is responsible for the activities of the Nuclear Energy Agency that support advancing the technical base of the safety of nuclear installations, has in recent years conducted an important activity in the CFD area. This activity has been carried out within the scope of the CSNI working group on the analysis and management of accidents (GAMA), and has mainly focused on the formulation of user guidelines and on the assessment and verification of CFD codes. It is in this GAMA framework that the present workshop was organized and carried out. The purpose of the workshop was to provide a forum for numerical analysts and experimentalists to exchange information in the field of NRS-related activities relevant to CFD validation, with the objective of providing input to GAMA CFD experts to create a practical, state-of-the-art, web-based assessment matrix on the use of CFD for NRS applications. Numerical simulations with a strong emphasis on validation were welcomed in such areas as heat transfer, buoyancy, stratification, natural circulation, free-surface modelling, turbulent mixing and multi-phase flow. These would relate to such NRS-relevant issues as: pressurized thermal shocks, boron dilution, hydrogen distribution, induced breaks, thermal striping, etc. The use of systematic error quantification and Best Practice Guidelines was encouraged. Papers reporting experiments providing high-quality data suitable for CFD validation, specifically in the area of NRS, were given high priority. Here, emphasis was placed on the availability of local measurements, especially multi-dimensional velocity measurements obtained using such techniques as laser-doppler velocimetry, hot

Gas reactor in-pile safety test project (GRIST-2)

International Nuclear Information System (INIS)

Kelley, A.P. Jr.; Arbtin, E.; St Pierre, R.

1979-01-01

Although out-of-pile tests may be expected to confirm individual phenomena models in core disruptive accident analysis codes, only in-pile tests are capable of verifying the extremely complex integrated model effects within the appropriate time phase for these accidents. For this reason, the GRIST-2 project, the purpose of which is to design and construct an in-pile helium loop capable of transient safety testing in the TREAT facility in Idaho, forms a cornerstone of the US GCFR safety program. The project organization, experiment program, facility, helium system design, and schedule which have been selected to meet the objectives are described

WINRE '92 - 3rd workshop on information management in nuclear safety, radiation protection, and environmental protection

International Nuclear Information System (INIS)

Hoepfner, K.A.

1993-01-01

The workshop puts much emphasis on the exchange of experience between experts from the West and from the Central and Eastern European countries. The representatives from the various countries and organisations are going to introduce their respective data banks, products, or services. The combination of papers and practical presentations will provide all with a qualified and comprehensive insight into the tried and tested as well as the new information management technologies in the specialist areas of nuclear safety, radiation protection, and environmental protection. Furthermore, it should also contribute to the promotion of the transfer of know-how between experts throughout the whole of Europe. (orig./DG)

Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Applications - Workshop Proceedings, CFD4NRS-3 - Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues

International Nuclear Information System (INIS)

2012-01-01

related to nuclear reactor safety issues. The conference consisted of 14 technical sessions. Among the topics included were containment, advanced reactors, multiphase flows, flow in a rod bundle, fire analysis, flows in dry casks, thermal analysis, mixing flows and pressurized thermal shock (PTS). About 1/3 of the papers were concerned with two-phase flow issues and the rest were devoted to single-phase CFD validation. South Korea is a candidate to host a follow-up meeting scheduled in 2012, organized by KAERI. KAERI also volunteered to sponsor and organize the second OECD/NEA CFD benchmark exercise. In the closure meeting after the panel session discussion, the representative from the Paul Scherrer Institut (PSI) proposed to host a future workshop scheduled for 2014, and to organize and sponsor the third OECD/NEA benchmark exercise based on a stratification experiment in the PANDA facility at PSI. The great majority of participants were interested in attending a follow-up workshop within two years. Comments were made during the panel session on the content of CFD4NRS-3. Two of the comments are that experiments can provide insight into the physics, and that CFD is now an accepted analysis tool, though it is very important to follow BPGs. There was a consensus on the need to maintain the high quality of the papers. The promotion of international benchmarking exercises for CFD was strongly encouraged. Another comment suggested that such workshops should be a forum to discuss novel approaches, but that one must also keep in mind that the end users are people from the nuclear safety community. The CFD4NRS, XCFD4NRS and CFD4NRS-3 workshops have proved to be very valuable means to assess the status of CFD code capabilities and validation, to exchange experiences in CFD code applications, and to monitor future progress

Safety cases for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van

2002-01-01

A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Institute for Safety Research. Annual report 1992

International Nuclear Information System (INIS)

Weiss, F.P.; Boehmert, J.

1993-11-01

The Institute is concerned with evaluating the design based safety and increasing the operational safety of technical systems which include serious sources of danger. It is further occupied with methods of mitigating the effects of incidents and accidents. For all these goals the institute does research work in the following fields: modelling and simulation of thermofluid dynamics and neutron kinetics in cases of accidents; two-phase measuring techniques; safety-related analyses and characterizing of mechanical behaviours of material; measurements and calculations of radiation fields; process and plant diagnostics; development and application of methods of decision analysis. This annual report gives a survey of projects and scientific contributions (e.g. Single rod burst tests with ZrNb1 cladding), lists publications, institute seminars and workshops, names the personal staff and describes the organizational structure. (orig./HP)

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

International Nuclear Information System (INIS)

Duckwitz, Noel

2011-01-01

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

Proceedings: Instrumentation and control test reduction workshop

International Nuclear Information System (INIS)

1991-09-01

Instrumentation and control (I ampersand C) surveillance and testing is a significant contributor to operations and management costs. Several techniques to eliminate or reduce manual testing requirements could reduce costs while improving plant safety and performance. I ampersand C test reduction was the subject of this 1991 workshop. The workshop covered test elimination, test reduction, test automation, and relevant standards and benefits. The conclusions of the workshop were the following: More utility information sharing is important. There is a significant amount of information available throughout the industry, but it is not available in a concise, useable form. An I ampersand C utility users group is needed to address items such as instrument calibration reduction, set-point methodologies, and other current I ampersand C issues. The workshop was well received. The timing is right to initiate actions to reduce testing

75 FR 4062 - Peer Review Best Practices Workshop

Science.gov (United States)

2010-01-26

... DEPARTMENT OF ENERGY Peer Review Best Practices Workshop AGENCY: Department of Energy, Office of..., demonstration and deployment programs and has used a variety of peer review approaches to select the best...'' for reviewing and selecting project proposals. The workshop will explore classic peer review processes...

Proceedings of the Canadian Gas Association's western operations workshop : readiness : reduce the risk

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

The natural gas industry is now facing a number of challenges related to energy infrastructure security and new regulations regarding pipeline and employee safety. Organized by the Canadian Gas Association (CGA), this workshop provided a forum for gas distribution companies, transmission companies, and service providers to discuss issues related to the delivery of natural gas in Canada. While the workshop also included tours and descriptions of specific natural gas facilities and operational centres, several of the breakout sessions during the workshop were used to discuss natural gas technologies and planning procedures related to safety and security. Planning process improvements using risk analysis for operations were discussed. Safety strategies for the 2010 Olympics relating to critical infrastructure protection were reviewed. Issues concerning emergency response preparedness were examined, as well as threats to energy infrastructure from acts of terrorism. Recent innovations in fire retardant clothing were presented. Technological innovations presented at the workshop included a cold weather technology line heater, and new technologies in underground pipe manufacturing. Human resources issues included new approaches to stress management and employee support and safety. The workshop featured 12 breakout sessions, of which 4 have been catalogued separately for inclusion in this database. refs., tabs., figs.

Safety of nuclear installations: Future direction

International Nuclear Information System (INIS)

1990-04-01

The Workshop presentations were divided into sessions devoted to the following topics: Environmental impact of fossil fuel energy technologies (5 papers), Future needs for nuclear power (7 papers), Safety objectives (10 papers), Safety aspects of the next generation of current-type nuclear power plants (8 papers), Safety aspects of new designs and concepts for nuclear power plants (6 papers), Special safety issues: Safety aspects of new designs and concepts for nuclear power plants (5 papers), Safety aspects of new designs and processes for the nuclear fuel cycle (5 papers), Closing panel (3 papers), 12 poster presentations and a Summary of the Workshop. A separate abstract was prepared for each of these papers. Refs, figs and tabs

Cloud/Fog Computing System Architecture and Key Technologies for South-North Water Transfer Project Safety

Directory of Open Access Journals (Sweden)

Yaoling Fan

2018-01-01

Full Text Available In view of the real-time and distributed features of Internet of Things (IoT safety system in water conservancy engineering, this study proposed a new safety system architecture for water conservancy engineering based on cloud/fog computing and put forward a method of data reliability detection for the false alarm caused by false abnormal data from the bottom sensors. Designed for the South-North Water Transfer Project (SNWTP, the architecture integrated project safety, water quality safety, and human safety. Using IoT devices, fog computing layer was constructed between cloud server and safety detection devices in water conservancy projects. Technologies such as real-time sensing, intelligent processing, and information interconnection were developed. Therefore, accurate forecasting, accurate positioning, and efficient management were implemented as required by safety prevention of the SNWTP, and safety protection of water conservancy projects was effectively improved, and intelligential water conservancy engineering was developed.

Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

Energy Technology Data Exchange (ETDEWEB)

MITCHELL, R.L.

2000-01-10

The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels.

Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

International Nuclear Information System (INIS)

MITCHELL, R.L.

2000-01-01

The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels

Safety assessment and regulatory strategy for NPP I and C modernization projects

International Nuclear Information System (INIS)

Manners, S.; Blocquel, Ch.

1999-10-01

IPSN is the technical support for the French nuclear safety authority (DSIN), but also acts independently. Through our participation at this IAEA meeting we wish to further our appreciation of the industry position for I and C modernization projects. We will present some of the concerns of the safety assessor and safety authority for such projects. We hope to share our experiences and views concerning current strategies for I and C modernization and licensing from. In our experience with NPP I and C programmes, the need for modification is most often not directly linked to safety. For our safety assessment we have to identify clearly and, as far as possible, categorize the safety relevance of the specified modifications and all safety impact in its implementation. Modernization can be simply for reasons of replacement of obsolete existing equipment or it can be linked to functional evolutions; safety functions may be directly or indirectly affected. The state of the art I and C solutions proposed by today's modernization programs have many benefits, but also pose a certain number of difficulties for the safety demonstration. On the implementation side, the safety assessment for a modernization project has to take into consideration specific issues compared with that for new plant. These include interface and compatibility with the existing installation, issues relating to 'on line' installation and commissioning, as well as operational issues concerning the changeover and trail periods. A further subject for discussion concerns how our regulatory requirements apply to modernization. We must as a minima comply with the requirements of the period. To what measure must we apply current or future (under development or for future reactor designs) standards? How can we tie in with requirements and legislation for new projects? Do we make a special case for back-fits? (authors)

Safety assessment and regulatory strategy for NPP I and C modernization projects

Energy Technology Data Exchange (ETDEWEB)

Manners, S.; Blocquel, Ch

1999-10-01

IPSN is the technical support for the French nuclear safety authority (DSIN), but also acts independently. Through our participation at this IAEA meeting we wish to further our appreciation of the industry position for I and C modernization projects. We will present some of the concerns of the safety assessor and safety authority for such projects. We hope to share our experiences and views concerning current strategies for I and C modernization and licensing from. In our experience with NPP I and C programmes, the need for modification is most often not directly linked to safety. For our safety assessment we have to identify clearly and, as far as possible, categorize the safety relevance of the specified modifications and all safety impact in its implementation. Modernization can be simply for reasons of replacement of obsolete existing equipment or it can be linked to functional evolutions; safety functions may be directly or indirectly affected. The state of the art I and C solutions proposed by today's modernization programs have many benefits, but also pose a certain number of difficulties for the safety demonstration. On the implementation side, the safety assessment for a modernization project has to take into consideration specific issues compared with that for new plant. These include interface and compatibility with the existing installation, issues relating to 'on line' installation and commissioning, as well as operational issues concerning the changeover and trail periods. A further subject for discussion concerns how our regulatory requirements apply to modernization. We must as a minima comply with the requirements of the period. To what measure must we apply current or future (under development or for future reactor designs) standards? How can we tie in with requirements and legislation for new projects? Do we make a special case for back-fits? (authors)

International Workshop on Post-Accident Food Safety Science, Hosted by the Cabinet Office, Government of Japan

International Nuclear Information System (INIS)

Tsukada, Hirofumi; Oikawa, Shinji; Aoki, Jin; Fujii, Masahiro; Okabe, Yoko; Koyama, Ryota; Iracane, Daniel; Lazo, Ted; ); Theelen, Rob; Sekiya, Naoya; Ito, Toshihiko; Kazumata, Seiichi; Hatta, Nobuyuki; Yuasa, Osamu; Nonaka, Shunkichi; Sato, Chie; Nisbet, Anne; Kai, Michiaki; Gusev, Igor; ); Nosske, Dietmar; Vandenhove, Hildegarde; Leonard, Kinson; Perks, Christopher; Liland, Astrid; Mostovenko, Andrei; Arai, Yoshimitsu; Sato, Mamoru; Kokubun, Youichi; Nemoto, Yoshiharu; Boyd, Mike; Homma, Toshimitsu; ); Lecomte, Jean Francois; Perks, Christopher

2016-11-01

monitoring/inspection has also been conducted for enormous samples every year. These measures have been combined to allow distribution of safe Japanese food. Many national governments and international organisations have focused on these issues since the accident. This workshop discusses the science supporting food safety standards, the science of managing contamination levels in food products to meet food safety standards, and the local, national and international organisational aspects to take into consideration to ensure food safety. This document is the compilation of the presentations (slides) given at the workshop in both English and Japanese languages

A desk evaluation review of project RAF/9/005 radiation protection development. Project desk evaluation

International Nuclear Information System (INIS)

1994-01-01

The Agency has been assisting member nations through a number of national TC projects in radiation protection and related areas over the years. In addition, a regional project RAF/9/005 - Radiation Protection Development (which is under this review) was approved in 1988, with the aim of assessing existing radiation protection practices in the African Member States in relation to the Agency's new basic safety standards for radiation protection, and to advise Governments on improvements. The project was subsequently extended up to 1994 as an umbrella project to assist all African Member States in the development of appropriate radiation protection services; to co-ordinate the implementation of the relevant national TC projects; and to develop co-operation amongst groups of Member States on a regional and sub-regional basis. Particular emphasis was to be given to manpower development through workshops, seminars and training courses in radiation protection and safety. In parallel thereto, the Agency's Radiation Protection Advisory Teams (RAPATs) visited nineteen African Member States during the period 1986 through 1993, to review and assess their radiation protection activities, identify priorities, and design long-term radiation protection programmes. RAPAT findings and recommendations were considered in drawing up programmes for implementation under project RAF/9/005

Ten year's activity in the field of neutron scattering workshop

International Nuclear Information System (INIS)

Hamaguchi, Yoshikazu

2003-01-01

'Neutron scattering' is in the frame of the 'Utilization of Research Reactor's of the FNCA (Forum for Nuclear Cooperation in Asia) project, which held the workshops from FY 1992. This report is a summary of the results and activities of neutron scattering workshops and sub-workshops since the start in FY 1992. (author)

DOE Ocean Carbon Sequestration Research Workshop 2005

Energy Technology Data Exchange (ETDEWEB)

Sarmiento, Jorge L. [Princeton Univ., NJ (United States); Chavez, Francisco [Monterey Bay Aquarium Research Inst. (MBARI), Moss Landing, CA (United States); Maltrud, Matthew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Adams, Eric [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Arrigo, Kevin [Stanford Univ., CA (United States). Dept. of Geophysics; Barry, James [Monterey Bay Aquarium Research Inst. (MBARI), Moss Landing, CA (United States); Carmen, Kevin [Louisiana State Univ., Baton Rouge, LA (United States); Bishop, James [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Bleck, Rainer [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gruber, Niki [Univ. of California, Los Angeles, CA (United States); Erickson, David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kennett, James [Univ. of California, Santa Barbara, CA (United States); Tsouris, Costas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Tagliabue, Alessandro [Lab. of Climate and Environmental Sciences (LSCE), Gif-sur-Yvette (France); Paytan, Adina [Stanford Univ., CA (United States); Repeta, Daniel [Woods Hole Oceanographic Inst. (WHOI), Woods Hole, MA (United States); Yager, Patricia L. [Univ. of Georgia, Athens, GA (United States); Marshall, John [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Gnanadesikan, Anand [Geophysical Fluid Dynamics Lab. (GFDL), Princeton, NJ (United States)

2007-01-11

The purpose of this proposal was to fund a workshop to bring together the principal investigators of all the projects that were being funded under the DOE ocean carbon sequestration research program. The primary goal of the workshop was to interchange research results, to discuss ongoing research, and to identify future research priorities. In addition, we hoped to encourage the development of synergies and collaborations between the projects and to write an EOS article summarizing the results of the meeting. Appendix A summarizes the plan of the workshop as originally proposed, Appendix B lists all the principal investigators who were able to attend the workshop, Appendix C shows the meeting agenda, and Appendix D lists all the abstracts that were provided prior to the meeting. The primary outcome of the meeting was a decision to write two papers for the reviewed literature on carbon sequestration by iron fertilization, and on carbon sequestration by deep sea injection and to examine the possibility of an overview article in EOS on the topic of ocean carbon sequestration.

Scientific-technical exchange of experiences between Germany and the GUS, the Baltic and MOE states, and central Asia and other regions. Workshop and establishment of a common knowledge base for nuclear safety and security. Final report; Wissenschaftlich-technischer Erfahrungsaustausch Deutschlands mit der GUS, den Baltischen und den MOE-Staaten sowie Laendern Zentralasiens und anderer Regionen. Arbeitstreffen und Schaffung gemeinsamer Wissensbasen fuer nukleare Sicherheit und Sicherung. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Dabrowski, Anna

2017-03-15

The report on the workshop concerning scientific-technical exchange of experiences between Germany and the GUS, the Baltic and MOE states, and central Asia and other regions includes the following issues: Results an d success of know-how transfer from West to East, topical issues for mutual exchange of experience, scope of the project, concept of the realization of mutual exchange of experiences. The emphasis of the workshop covered the following issues: emergency preparedness, international requirements concerning nuclear safety and radiation protection, transport of radioactive wastes and communication in nuclear technology.

Instrumentation for the advanced high-flux reactor workshop: proceedings

International Nuclear Information System (INIS)

Moon, R.M.

1984-01-01

The purpose of the Workshop on Instrumentation for the Advanced High-Flux Reactor, held on May 30, 1984, at the Oak Ridge National Laborattory, was two-fold: to announce to the scientific community that ORNL has begun a serious effort to design and construct the world's best research reactor, and to solicit help from the scientific community in planning the experimental facilities for this reactor. There were 93 participants at the workshop. We are grateful to the visiting scientists for their enthusiasm and interest in the reactor project. Our goal is to produce a reactor with a peak thermal flux in a large D 2 O reflector of 5 x 10 15 n/cm 2 s. This would allow the installation of unsurpassed facilities for neutron beam research. At the same time, the design will provide facilities for isotope production and materials irradiation which are significantly improved over those now available at ORNL. This workshop focussed on neutron beam facilities; the input from the isotope and materials irradiation communities will be solicited separately. The reactor project enjoys the full support of ORNL management; the present activities are financed by a grant of $663,000 from the Director's R and D Fund. However, we realize that the success of the project, both in realization and in use of the reactor, depends on the support and imagination of a broad segment of the scientific community. This is more a national project than an ORNL project. The reactor would be operated as a national user facility, open to any research proposal with high scientific merit. It is therefore important that we maintain a continuing dialogue with outside scientists who will be the eventual users of the reactor and the neutron beam facilities. The workshop was the first step in establishing this dialogue; we anticipate further workshops as the project continues

Safety risk assessment using analytic hierarchy process (AHP) during planning and budgeting of construction projects.

Science.gov (United States)

Aminbakhsh, Saman; Gunduz, Murat; Sonmez, Rifat

2013-09-01

The inherent and unique risks on construction projects quite often present key challenges to contractors. Health and safety risks are among the most significant risks in construction projects since the construction industry is characterized by a relatively high injury and death rate compared to other industries. In construction project management, safety risk assessment is an important step toward identifying potential hazards and evaluating the risks associated with the hazards. Adequate prioritization of safety risks during risk assessment is crucial for planning, budgeting, and management of safety related risks. In this paper, a safety risk assessment framework is presented based on the theory of cost of safety (COS) model and the analytic hierarchy process (AHP). The main contribution of the proposed framework is that it presents a robust method for prioritization of safety risks in construction projects to create a rational budget and to set realistic goals without compromising safety. The framework provides a decision tool for the decision makers to determine the adequate accident/injury prevention investments while considering the funding limits. The proposed safety risk framework is illustrated using a real-life construction project and the advantages and limitations of the framework are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

International Nuclear Information System (INIS)

Armstrong, D.L.

1994-08-01

This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment

Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

Energy Technology Data Exchange (ETDEWEB)

Armstrong, D.L.

1994-08-01

This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

Nordic projects in the field of nuclear safety

International Nuclear Information System (INIS)

Soerensen, H.C.

1989-07-01

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

Nordic projects in the field of nuclear safety

International Nuclear Information System (INIS)

Soerensen, H.C.

1988-05-01

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

Diversifying Geoscience by Preparing Faculty as Workshop Leaders to Promote Inclusive Teaching and Inclusive Geoscience Departments

Science.gov (United States)

Macdonald, H.; Manduca, C. A.; Beane, R. J.; Doser, D. I.; Ebanks, S. C.; Hodder, J.; McDaris, J. R.; Ormand, C. J.

2017-12-01

Efforts to broaden participation in the geosciences require that faculty implement inclusive practices in their teaching and their departments. Two national projects are building the capacity for faculty and departments to implement inclusive practices. The NAGT/InTeGrate Traveling Workshops Program (TWP) and the Supporting and Advancing Geoscience Education in Two-Year Colleges (SAGE 2YC) project each prepares a cadre of geoscience educators to lead workshops that provide opportunities for faculty and departments across the country to enhance their abilities to implement inclusive teaching practices and develop inclusive environments with the goal of increasing diversity in the geosciences. Both projects prepare faculty to design and lead interactive workshops that build on the research base, emphasize practical applications and strategies, enable participants to share their knowledge and experience, and include time for reflection and action planning. The curriculum common to both projects includes a framework of support for the whole student, supporting all students, data on diversity in the geosciences, and evidence-based strategies for inclusive teaching and developing inclusive environments that faculty and departments can implement. Other workshop topics include classroom strategies for engaging all students, addressing implicit bias and stereotype threat, and attracting diverse students to departments or programs and helping them thrive. Online resources for each project provide support beyond the workshops. The TWP brings together educators from different institutional types and experiences to develop materials and design a workshop offered to departments and organizations nationwide that request the workshop; the workshop leaders then customize the workshop for that audience. In SAGE 2YC, a team of leaders used relevant literature to develop workshop materials intended for re-use, and designed a workshop session for SAGE 2YC Faculty Change Agents, who

Russian-Indian Workshop "Radio Astronomy And Star Formation"

Science.gov (United States)

Zinchenko, Igor; Zemlyanukha, P.

2017-09-01

In recent years the Russian Foundation for Basic Research and the Department of Science and Technology of the Government of India supported several joint projects in this field. The aims of the workshop were a discussion of the results of these and other relevant projects and promotion of the further Russian-Indian cooperation in this rapidly developing area of astrophysical research. The participants of the workshop represented several Russian and Indian organizations, which have important results in this field. The scientific program included a wide range of relevant observational and theoretical studies. The organizers of the workshop hope that the vivid discussions and tight communications between the participants will lead to increasing cooperation in this field between Russian and Indian researchers.

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

Science.gov (United States)

Nadell, Shari-Beth

2003-01-01

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

International movement on radiation safety related to the ICRP and the IAEA-RADWASS

International Nuclear Information System (INIS)

Kosako, Toshiso

1994-01-01

Nowadays discussion on Radiation Safety has a spread of world wide range. The main framework on radiation safety was constructed by ICRP (International Commission on Radiological Protection), which was established in 1928. This term of the committee was from June 1993 to May 1997 and the first plenary meeting was held at the Queen's hotel in Bournemouth of the United Kingdom on September 1993. The outline of this meeting, especially related items to the Committee 4, were summarized in this paper. The second point of our workshop considerations is radioactive waste problems, which are now under discussion in RADWASS (Radioactive Waste Safety Standards) project of IAEA (International Atomic Energy Agency). This IAEA-RADWASS will last nearly 10 years to cover whole subjects. These discussed items are arranged into various international standards; the safety fundamental, the safety standards, the safety guides and the safety practices. These systematic approach, if we could summarize, would be effective not only to the specialists but also to a general public to get an acceptance of radioactive waste problem. Here, this IAEA-RADWASS project is reviewed. (author)

HySafe research priorities workshop report Summary of the workshop organized in cooperation with US DOE and supported by EC JRC in Washington DC November 10-11 2014.

Energy Technology Data Exchange (ETDEWEB)

Jay Keller; Laura Hill; Kristian Kiuru; Groth, Katrina M.; Hecht, Ethan; Will James

2016-03-01

The HySafe research priorities workshop is held on the even years between the International Conference on Hydrogen Safety (ICHS) which is held on the odd years. The research priorities workshop is intended to identify the state-of-the-art in understanding of the physical behavior of hydrogen and hydrogen systems with a focus on safety. Typical issues addressed include behavior of unintended hydrogen releases, transient combustion phenomena, effectiveness of mitigation measures, and hydrogen effects in materials. In the workshop critical knowledge gaps are identified. Areas of research and coordinated actions for the near and medium term are derived and prioritized from these knowledge gaps. The stimulated research helps pave the way for the rapid and safe deployment of hydrogen technologies on a global scale. To support the idea of delivering globally accepted research priorities for hydrogen safety the workshop is organized as an internationally open meeting. In attendance are stakeholders from the academic community (universities, national laboratories), funding agencies, and industry. The industry participation is critically important to ensure that the research priorities align with the current needs of the industry responsible for the deployment of hydrogen technologies. This report presents the results of the HySafe Research Priorities Workshop held in Washing- ton, D.C. on November 10-11, 2014. At the workshop the participants presented updates (since the previous workshop organized two years before in Berlin, Germany) of their research and development work on hydrogen safety. Following the workshop, participants were asked to provide feedback on high-priority topics for each of the research areas discussed and to rank research area categories and individual research topics within these categories. The research areas were ranked as follows (with the percentage of the vote in parenthesis): 1. Quantitative Risk Assessment (QRA) Tools (23%) 2. Reduced Model

75 FR 71454 - NIJ Certification Programs Workshop

Science.gov (United States)

2010-11-23

... Workshop to introduce NIJ standards for law enforcement, corrections, and public safety equipment to....m. to 5 p.m. at the Hotel Monaco, 700 F Street, NW., Washington, DC 20004. The meeting room is the...

Proceedings: 2001 Nuclear Asset Management Workshop

International Nuclear Information System (INIS)

2002-01-01

The fourth annual EPRI Nuclear Asset Management Workshop helped decision makers at all levels of nuclear enterprises to keep informed about developing nuclear asset management (NAM) processes, methods, and tools. The goal is to operate nuclear plants with enhanced profitability, while maintaining safety

Methods and criteria for safety analysis (FIN L2535)

International Nuclear Information System (INIS)

1992-12-01

In response to the NRC request for a proposal dated October 20, 1992, Westinghouse Savannah River Company (WSRC) submit this proposal to provide contractural assistance for FIN L2535, ''Methods and Criteria for Safety Analysis,'' as specified in the Statement of Work attached to the request for proposal. The Statement of Work involves development of safety analysis guidance for NRC licensees, arranging a workshop on this guidance, and revising NRC Regulatory Guide 3.52. This response to the request for proposal offers for consideration the following advantages of WSRC in performing this work: Experience, Qualification of Personnel and Resource Commitment, Technical and Organizational Approach, Mobilization Plan, Key Personnel and Resumes. In addition, attached are the following items required by the NRC: Schedule II, Savannah River Site - Job Cost Estimate, NRC Form 189, Project and Budget Proposal for NRC Work, page 1, NRC Form 189, Project and Budget Proposal for NRC Work, page 2, Project Description

Description of data-sources used in SafetyCube, Deliverable 3.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Hagström, L. Thomson, R. Hermitte, T. Weijermars, W. Bos, N. Talbot, R. Thomas, P. Dupont, E. Martensen, H. Bauer, R. Hours, M. Høye, E. Jänsch, M. Murkovic, A. Niewöhner, W. Papadimitriou, E. Pérez, C. Phan, V. Usami, D. & Vázquez-de-Prada, J.

2017-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

Nuclear safety research project (PSF). 1999 annual report

International Nuclear Information System (INIS)

Muehl, B.

2000-08-01

The reactor safety R and D work of the Karlsruhe Research Centre (FZK) has been part of the Nuclear Safety Research Project (PSF) since 1990. The present annual report summarizes the R and D results of PSF during 1999. The research tasks cover three main topics: Light Water Reactor safety, innovative systems, and studies related to the transmutation of actinides. The importance of the Light Water Reactor safety, however, has decreased during the last year in favour of the transmutation of actinides. Numerous institutes of the research centre contribute to the PSF programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2000. (orig.) [de

Transport fire safety engineering in the European Union - project TRANSFEU

Directory of Open Access Journals (Sweden)

Jolanta Maria RADZISZEWSKA-WOLIŃSKA

2011-01-01

Full Text Available Article presents European Research project (of FP7-SST-2008-RTD-1 for Surface transportation TRANSFEU. Projects undertakes to deliver both a reliable toxicity measurement methodology and a holistic fire safety approach for all kind of surface transport. It bases on a harmonized Fire Safety Engineering methodology which link passive fire security with active fire security mode. This all embracing system is the key to attain optimum design solutions in respect to fire safety objectives as an alternative to the prescriptive approach. It will help in the development of innovative solutions (design and products used for the building of the surface transport which will better respect the environment.In order to reach these objectives new toxicity measurement methodology and related classification of materials, new numerical fire simulation tools, fire test methodology (laboratory and full scale and a decisive tool to optimize or explore new design in accordance to the fire safety requirements will be developed.

UMTRA project office federal employee occupational safety and health program plan

International Nuclear Information System (INIS)

1994-06-01

This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

The action of the project coordinator with respect to reactor safety

International Nuclear Information System (INIS)

Leclercq, Jacques

1981-01-01

Before describing the various actions of the project coordinator (EDF) entrusted with the building of nuclear power stations, with respect to reactor safety in France, the definition of reactor safety and the various participants are mentioned first. These participants are: the Government Departments and the Experts involved (the Department of Nuclear Safety of the 'Institut de Protection et de Surete Nucleaire' forming the first technical support) and the applicant, namely the EDF. The reactor safety actions of the project coordinator are defined as from the following components: 1 - The targets laid down with respect to safety, the final objective being the protection of workers and the public against the potential dangers of the installations, principally against radiation. 2 - The safety methodology at the design stage of the power station: 'barrier' method, defence method in depth at three levels, lines of assurance method, and probabilistic method. 3 - Safety actions at the construction stage within the context of an assurance of quality programe. 4 - Safety at the trials, commissioning and operating stage, with the backing of the 'Groupe Operationnel de Demarrage (G.O.D.)' and the 'Commission d'Essais sur Site (C.E.S.)'. An initial balance sheet of the reactor safety actions for the PWR units built by the EDF is presented [fr

Safety assessment of ammonia as a transport fuel

Energy Technology Data Exchange (ETDEWEB)

Duijm, N.J.; Markert, F.; Lundtang paulsen, Jette

2005-02-01

This report describes the safety study performed as part of the EU supported project 'Ammonia Cracking for Clean Electric Power Technology' The study addresses the following activities: safety of operation of the ammonia-powered vehicle under normal and accident (collision) conditions, safety of transport of ammonia to the refuelling stations and safety of the activities at the refuelling station (unloading and refuelling). Comparisons are made between the safety of using ammonia and the safety of other existing or alternative fuels. The conclusion is that the hazards in relation to ammonia need to be controlled by a combination of technical and regulatory measures. The most important requirements are: - Advanced safety systems in the vehicle - Additional technical measures and regulations are required to avoid releases in maintenance workshops and unauthorised maintenance on the fuel system - Road transport of ammonia to refuelling stations in refrigerated form - Sufficient safety zones between refuelling stations and residential or otherwise public areas. When these measures are applied, the use of ammonia as a transport fuel wouldnt cause more risks than currently used fuels (using current practice). (au)

Radioactive waste management in Spain: co-ordination and projects

International Nuclear Information System (INIS)

2007-01-01

The sixth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ENRESA, the Spanish agency responsible for the management of radioactive waste and the dismantling of nuclear power plants, and the Council of Nuclear Safety (CSN), with the support of the Association of Spanish Municipalities in Areas Surrounding Nuclear Power Plants (AMAC). The workshop took place at L'Hospitalet de l'Infant, Catalonia, Spain, on 21-23 November 2005. At this workshop, Spanish stakeholders and delegates from 14 countries discussed current co-ordination of radioactive waste management decision making in Spain. Findings were shared from Cowam-Spain, a co-operative research project on the involvement of local stakeholders, the relationship between national and local levels of decision making, and the long-term sustainability of decisions regarding the siting of a centralized interim storage facility for high-level waste. These proceedings include the workshop presentations and discussions, as well as the rapporteurs' reflections on what was learned about policy making and participative decision making. (author)

Annual report on reactor safety research projects. Reporting period 2011. Progress report

International Nuclear Information System (INIS)

2011-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects. Reporting period 2014. Progress report

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Annual report on reactor safety research projects. Reporting period 2013. Progress report

International Nuclear Information System (INIS)

2013-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects. Reporting period 2015. Progress report

International Nuclear Information System (INIS)

2015-01-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft tor Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are ·' prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. it has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

UMTRA Project: Environment, Safety, and Health Plan

International Nuclear Information System (INIS)

1995-02-01

The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project's ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors' evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations

Spent Nuclear Fuel (SNF) Project Safety Basis Implementation Strategy

International Nuclear Information System (INIS)

TRAWINSKI, B.J.

2000-01-01

The objective of the Safety Basis Implementation is to ensure that implementation of activities is accomplished in order to support readiness to move spent fuel from K West Basin. Activities may be performed directly by the Safety Basis Implementation Team or they may be performed by other organizations and tracked by the Team. This strategy will focus on five key elements, (1) Administration of Safety Basis Implementation (general items), (2) Implementing documents, (3) Implementing equipment (including verification of operability), (4) Training, (5) SNF Project Technical Requirements (STRS) database system

The use of living PSA in safety management, a procedure developed in the nordic project ''safety evaluation, NKS/SIK-1''

International Nuclear Information System (INIS)

Johanson, G.; Holmberg, J.

1994-01-01

The essential objective with the development of a living PSA concept is to bring the use of the plant specific PSA model out to the daily safety work to allow operational risk experience feedback and to increase the risk awareness of the intended users. This paper will present results of the Nordic project ''Safety Evaluation, NKS/SIK-1''. The SIK-1 project has defined and demonstrated the practical use of living PSA for safety evaluation and for identification of possible improvements in operational safety. Subjects discussed in this paper are dealing with the practical implementation and use of PSA to make proper safety related decisions and evaluation. (author). 24 refs, 1 fig., 1 tab

The HUPO Brain Proteome project wish list--summary of the 9(th) HUPO BPP Workshop 9-10 January 2008, Barbados.

Science.gov (United States)

Hamacher, Michael; Eisenacher, Martin; Tribl, Florian; Stephan, Christian; Marcus, Katrin; Hardt, Tanja; Wiltfang, Jens; Martens, Lennart; Desiderio, Dominic; Gutstein, Howard; Park, Young Mok; Meyer, Helmut E

2008-06-01

The Human Brain Proteome Project (HUPO BPP) aims at advancing knowledge and the understanding of neurodiseases and aging with the purpose of identifying prognostic and diagnostic biomarkers, as well as to push new diagnostic approaches and medications. The participating groups meet in semi-annual workshops to discuss the progress, as well as the needs, within the field of proteomics. The 9(th) HUPO BPP workshop took place in Barbados from 9-10 January, 2008. Discussing the future HUPO BPP Roadmap, the attendees drafted the so called HUPO BPP wish list containing timelines, suggestions and missions. This wish list will be updated regularly and will serve as a guideline for the next phase.

Dissemination material template, Deliverable 2.2 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Tros, M. & Houtenbos, M.

2016-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

Project W-030 safety class upgrade summary report

International Nuclear Information System (INIS)

Kriskovich, J.R.

1998-01-01

This document presents a summary of safety class criteria for the 241-AY/AZ Tank Farm primary ventilation system upgrade under Project W-030, and recommends acceptance of the system as constructed, based on a review of supporting documentation

Development of a Safety Management Web Tool for Horse Stables.

Science.gov (United States)

Leppälä, Jarkko; Kolstrup, Christina Lunner; Pinzke, Stefan; Rautiainen, Risto; Saastamoinen, Markku; Särkijärvi, Susanna

2015-11-12

Managing a horse stable involves risks, which can have serious consequences for the stable, employees, clients, visitors and horses. Existing industrial or farm production risk management tools are not directly applicable to horse stables and they need to be adapted for use by managers of different types of stables. As a part of the InnoEquine project, an innovative web tool, InnoHorse, was developed to support horse stable managers in business, safety, pasture and manure management. A literature review, empirical horse stable case studies, expert panel workshops and stakeholder interviews were carried out to support the design. The InnoHorse web tool includes a safety section containing a horse stable safety map, stable safety checklists, and examples of good practices in stable safety, horse handling and rescue planning. This new horse stable safety management tool can also help in organizing work processes in horse stables in general.

The spin project: safety and performance indicators in different time frames

International Nuclear Information System (INIS)

Storck, R.; Becker, D.A.

2002-01-01

Safety and performance indicators have been under discussion for many years in several countries and international organisations. If those indicators refer to the long term safety of the total disposal system, they are often called safety indicators. If they refer to the performance of subsystems or the total system from a more technical point of view, they are sometimes called performance indicators. The need for indicators other than dose rates derives e.g. from the long time frames involved in safety assessments of waste disposal systems and the increasing uncertainty in dose rate calculations over time due to uncertainty in evolution of the surface environment and of behaviour of man. Before introducing additional indicators into a safety case of a potential repository site, the applicability and usefulness of different indicators have to be investigated and evaluated. The systematic analysis and testing of safety and performance indicators for use in different time horizons after closure of the disposal facility is the task of the SPIN project. This is done by re-calculating four recent studies concerning repository projects in granite formations. (authors)

Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5). Workshop Proceedings, 9-11 September 2014, Zurich, Switzerland

International Nuclear Information System (INIS)

Smith, Brian L.; Andreani, Michele; Badillo, Arnoldo; Dehbi, Abdel; Sato, Yohei; Smith, Brian L.; Dreier, Joerg; Kapulla, Ralf; Niceno, Bojan; Sharabi, Medhat; Bestion, Dominique; Bieder, Ulrich; Coste, Pierre; Martinez, Jean Marc; Zigh, Ghani; Boyd, Chris; Prasser, Horst-Michael; Kerenyi, Nora; Adams, Robert; Bolesch, Christian; D'Aleo, Paolo; Eismann, Ralph; Kickhofel, John; Lafferty, Nathan; Saxena, Abhishek; Kissane, Martin; ); Ulses, Anthony; ); Bartosiewicz, Yann; Seynhaeve, Jean-Marie; Caraghiaur, Diana; Munoz Cobo, Jose Luis; Glaeser, Horst; Buchholz, Sebastian; Scheuerer, Martina; Hassan, Yassin; In, Wang-Kee; Song, Chul-Hwa; Yoon, Han-Young; Kim, J.W.; Koncar, Bostjan; Tiselj, Iztoc; Lakehal, Djamel; Yadigaroglu, George; Lo, Simon; Manera, Annalisa; Petrov, Victor; Mimouni, Stephane; Benhamadouche, Sofiane; Morii, Tadashi; Suikkanen, Heikki; Toppila, Timo; Angele, Kristian; Baglietto, Emilio; Cheng, Xu; Graffard, Estelle; Ko, Jordan; Hoehne, Thomas; Lucas, Dirk; Krepper, Eckhard; Laurien, Eckart; Moretti, Fabio; Piro, Markus; Roelofs, Ferry; Veber, Pascal; Watanabe, Tadashi; Yan, Jin; Yeoh, Guan

2016-01-01

This present workshop, the 5. Computational Fluid Dynamics for Nuclear-Reactor Safety (CFD4NRS-5), in the biennial series of such Nuclear Energy Agency (NEA) and International Atomic Energy Agency (IAEA) sponsored events, a tradition which began in Garching in 2006, follows the format and objectives of its predecessors in creating a forum whereby numerical analysts and experimentalists can exchange information in the application of computational fluid dynamics (CFD) to nuclear power plant (NPP) safety and future design issues. The emphasis, as always, was, in a congenial atmosphere, to offer exposure to state-of-the-art (single-phase and multi-phase) CFD applications reflecting topical issues arising in NPP design and safety, but in particular to promote the release of high-resolution experimental data to continue the CFD validation process in this application area. The reason for the increased use of multi-dimensional CFD methods is that a number of important thermal-hydraulic phenomena occurring in NPPs cannot be adequately predicted using traditional one-dimensional system hydraulics codes with the required accuracy and spatial resolution when strong three-dimensional motions prevail. Established CFD codes already contain empirical models for simulating turbulence, heat transfer, multi-phase interaction and chemical reactions. Nonetheless, such models must be validated against test data before they can be used with confidence. The necessary validation procedure is performed by comparing model predictions against trustworthy experimental data. However, reliable model assessment requires CFD simulations to be undertaken with full control over numerical errors and input uncertainties. The writing groups originally set up by the NEA have been consistently promoting the use of best practice guidelines (BPGs) in the application of CFD for just this purpose, and BPGs remain a central pillar of the simulation material accepted at this current workshop, as it was at its

Probabilistic Safety Assessment (PSA) of Natural External Hazards Including Earthquakes. Workshop Proceedings, Prague, Czech Republic, 17-20 June 2013

International Nuclear Information System (INIS)

2014-01-01

The Fukushima Dai-ichi accident triggered discussions about the significance of external hazards and their treatment in safety analyses. In addition, stress tests results have shown vulnerabilities and potential of cliff-edge effects in plant responses to external hazards and have identified possibilities and priorities for improvements and safety measures' implementation at specific sites and designs. In order to address these issues and provide relevant conclusions and recommendations to CSNI and CNRA, the CSNI Working Group on Risk Assessment (WGRISK) directed, in cooperation with the CSNI Working Group on Integrity and Ageing of Components and Structures (WGIAGE), a workshop hosted by UJV Rez. The key objectives of the workshop were to collect information from the OECD member states on methods and approaches being used, and experience gained in probabilistic safety assessment of natural external hazards, as well as to support the fulfillment of the CSNI task on 'PSA of natural external hazards including earthquakes'. These objectives are described more in detail in the introduction in Chapter 1 of this report. The WGRISK activities preceding the workshop and leading to the decision to organize it are described in Chapter 2 of this report. The focus of the workshop was on external events PSA for nuclear power plants, including all modes of operation. The workshop scope was generally limited to external, natural hazards, including those hazards where the distinction between natural and man-made hazards is not sharp. The detailed information about the presentations, discussions, and results of the workshop is presented in Chapter 3 of this report. Some general conclusions were agreed on during the workshop, which are presented in the following paragraphs. - The lessons learned from the Fukushima Dai-ichi reactor accidents and related actions at the national, regional, and global level have emphasized the importance to assess risks associated (authors) with

Proceedings of the nuclear criticality technology safety project

Energy Technology Data Exchange (ETDEWEB)

Sanchez, R.G. [comp.

1997-06-01

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

Proceedings of the nuclear criticality technology safety project

International Nuclear Information System (INIS)

Sanchez, R.G.

1997-06-01

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

Proceedings of the Flat-Plate Solar Array Project Workshop on Crystal Gowth for High-Efficiency Silicon Solar Cells

Science.gov (United States)

Dumas, K. A. (Editor)

1985-01-01

A Workshop on Crystal Growth for High-Efficiency Silicon Solar Cells was held December 3 and 4, 1984, in San Diego, California. The Workshop offered a day and a half of technical presentations and discussions and an afternoon session that involved a panel discussion and general discussion of areas of research that are necessary to the development of materials for high-efficiency solar cells. Topics included the theoretical and experimental aspects of growing high-quality silicon crystals, the effects of growth-process-related defects on photovoltaic devices, and the suitability of various growth technologies as cost-effective processes. Fifteen invited papers were presented, with a discussion period following each presentation. The meeting was organized by the Flat-Plate Solar Array Project of the Jet Propulsion Laboratory. These Proceedings are a record of the presentations and discussions, edited for clarity and continuity.

Urban-architectural workshop as an opportunity for theoretical reflection: Example of the international urban-architectural workshop Maribor-South

Directory of Open Access Journals (Sweden)

Peter Šenk

2013-07-01

Full Text Available The paper presents the international urban-architectural workshop Maribor-South (2010-11 as a model for “Maribor’s” urban-architectural workshops, which urban planners evaluate and use to direct urban development and theoretical discussion. The presented interdisciplinary project explored possibilities for designing the southern edge of the city in the area where the southern bypass construction is planned. In addition describing the example of the workshop, which develops the theoretical field through a “practical and project approach” with the defined project basis, i.e. the defined area of discussion and project issue, the paper also highlights the opportunity for a “theoretical approach”. The theoretical approach aims at providing a wider insight into the related theoretical field based on a generalised spatial issue. As one of the key priorities of contemporary urban planning and sustainable urban redevelopment, the planned direction of urban development in the areas of constructing transport infrastructure, which is evident in the first approach, moves into a wider referential field (no longer directly related to the project with the second approach by examining the issues of mobility, space, place, diversity of infrastructures of contemporary space, etc. While in the first approach developing design concepts strives for theoretical conceptualisation, the second approach facilitates focusing on finding links between the theoretical concept and manifestations in real space, though the approaches are always separated. Their operationality is possible only on the level of “combinatorial thinking” and remains beyond direct instrumentality.

The modification of main steam safety valves in Qinshan phase Ⅱ expansion project

International Nuclear Information System (INIS)

Chen Haiqiao

2012-01-01

The main steam safety valves of NPP steam system are second- class nuclear safety component. It used to limit the pressure of SG secondary side and main steam system via emitting steam into the environment. At present, the main steam safety valves have mechanical valves and assisted power valves. According to the experience of power plants at home and abroad, including Qinshan Phase Ⅱ unit 1/2 experience feedback, Qinshan Phase Ⅱ expansion project made modification on valve type, setting value and valve body. This paper introduce the characteristics of different safety valve types, the modification of main steam safety valves and the modification analysis on safety issues.security and impact on the other systems in Qinshan Phase Ⅱ expansion project. (author)

KfK Nuclear Safety Project. First semiannual report 1985

International Nuclear Information System (INIS)

1985-11-01

The semiannual progress report 1985/1 is a description of work within the Nuclear Safety Project performed in the first six month of 1985 in the nuclear safety field by KfK institutes and departements and by external institutions on behalf of KfK. The chosen kind of this report is that of short summaries, containing the topics: work performed, results obtained and plans for future work. (orig./HP) [de

CNRA/CSNI workshop on licensing and operating experience of computer-based I and C systems - Summary and conclusions

International Nuclear Information System (INIS)

2002-01-01

The OECD Workshop on Licensing and Operating Experience of Computer-Based I and C Systems, was sponsored by both the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Czech State Office for Nuclear Safety (SUJB), the Czech Power Board CEZ a.s., I and C Energo a.s. and the Nuclear Research Institute, Rez near Prague. The objectives of the Workshop were to exchange the experience gained by both the regulators and the industry in different countries in the licensing and operation of computer-based I and C systems, to discuss the existing differences in their licensing approaches in various countries, to consider the safety aspects of their practical use, and to discuss the ways of promoting future international co-operation in the given area. The scope of the Workshop included: - review of the progress made since the CNRA/CSNI workshop which was held in 1996 - current and future regulatory needs and/or requirements for the computer-based I and C systems - progress made in software life cycle activities, including verification and validation, and safety/hazards analysis - benefits of applying the computer-based I and C systems to improve plant performance and safety. The Technical Sessions and Discussion Sessions covered the following topics: Opening Session: Advances made in the use and planning of computer-based I and C systems; Topic 1: National and international standards and guides for computer-based safety systems; Topic 2: Regulatory aspects; Topic 3: Analysis and assessment of digital I and C systems; Topic 4: Software life cycle activities; Topic 4: Experience with applications, system aspects, potential limits and future trends and needs; Final Session: Workshop summary. The workshop provided a unique opportunity for people with experience in licensing, developing, manufacturing, implementing, maintaining or

Incorporation of occupational health and safety in cleaner production projects in South Africa

DEFF Research Database (Denmark)

Hedlund, Frank Huess

2002-01-01

The purpose of this research is to reveal ways in which occupational health and safety can be integrated in environmental cleaner production projects. Of particular interest are those cleaner production projects that are run by the Danish government's environmental assistance agency, Danced......, in South Africa.The study explores two main avenues of integration. First, integrating through better planning, focussing at the tools and procedures in use by Danced for project management -- integrating occupational health and safety into the project specification, so to speak.Second, integrating...... occupational health and safety into the environmental activities that take place at company level. Two ways of doing so are explored, the main distinction being company size. For large companies, integration of management systems may be attractive. For small companies, integration into a less formal network...

Special Characteristics of the Rust Workshop and Their Influence on My Facilitation Process.

Science.gov (United States)

Bowen, Maria Villas-Boas

1987-01-01

Evaluates the Carl Rogers Peace Project workshop held in Austria in 1985. Defines ways in which the workshop was unique. Elaborates on staff participation and the author's personal reactions. Concludes by discussing the distinctive role facilitators had in this workshop. (BR)

Summary of experimental insertions workshop

International Nuclear Information System (INIS)

Sandweiss, J.; Month, M.

1976-01-01

The last ISABELLE workshop of the summer 1976 series, which was held at Brookhaven, August 16-20, focused on the design and utilization of the experimental insertions. The goals of the workshop, which were somewhat more general than might be suggested by the title, are: (1) review the ISABELLE proposal from the point of view of experimental use; (2) contribute useful information on the ''open questions'' in the ISABELLE design; (3) develop data for experimental equipment and operating cost estimates; and (4) project a first approximation to ISABELLE operating modes

MesonNet Workshop on Meson Transition Form Factors

CERN Document Server

Eidelman, S; Hanhart, C; Kubis, B; Kupsc, A; Leupold, S; Moskal, P; Schadmand, S

2012-01-01

The mini-proceedings of the Workshop on Meson Transition Form Factors held in Cracow from May 29th to 30th, 2012 introduce the meson transition form factor project with special emphasis on the interrelations between the various form factors (on-shell, single off-shell, double off-shell). Short summaries of the talks presented at the workshop follow.

The ROS Workshop

CERN Multimedia

Francis, D.

The first week of February saw the taking place of the ReadOut Subsystem (ROS) workshop. The ROS is the subsystem of the Trigger, DAQ & DCS project which receives and buffers data from the detector ReadOut Drivers (RODs). On request it then provides a subset of this buffered data, the so-called Regions of Interest (RoI), to the Level 2 trigger. Using the subsequent Level 2 trigger decision, the ROS either removes the buffered event data from its buffers or sends the full event data to the Event Filter for further processing. The workshop took place over a four-day period at a location in the Jura. The average daily attendance was twenty people, which mainly represented the five main ATLAS institutes currently engaged in this Trigger, DAQ & DCS activity. The aim of the workshop was to bring to an end the current prototyping activities in this area and launch the next, final, phase of prototyping. This new phase of prototyping will build on the successful activities of the previous phase and will focus...

JRC/IE support activities to PHARE nuclear safety programmes. Dissemination of PHARE project results

International Nuclear Information System (INIS)

Ranguelova, V.; Pla, P.; Rieg, C.; Bieth, M.

2005-01-01

Nuclear safety in Europe is one of European Union's primary concerns, therefore the European Union decided to take a prominent role to help the New Independent States and countries of Central and Eastern Europe to ensure the safety of their nuclear reactors. The European Union TACIS and PHARE programmes in nuclear safety have been undertaken since 1990. The European Commission's Directorate General External Relations (EC DG RELEX) and, Directorate General Europe Aid Co-operation Office (EC DG AIDCO), are responsible for programming and management of implementation of TACIS projects. Directorate General Enlargement (EC DG ELARG) is responsible for programming PHARE programmes, but implementation of most projects has been decentralised since 1999 budget year to the Beneficiary countries. DG ELARG acts as backstopping for the relevant EC Delegations. In these activities, the TSSTP Unit at the JRC/IE in Petten, The Netherlands, is a technical and scientific adviser of DG RELEX and DG AIDCO and provides support to DG ELARG for very specific technical issues. Several PHARE projects aiming at improving nuclear safety have been successfully implemented for a number of plants from Central and Eastern Europe. In some cases major safety issues have been addressed by means of multi-country projects and results have been disseminated to the rest of the nuclear community. Although a lot of information has been exchanged at a bilateral level, further effort is needed to collect the project results in a systematic way and make them available by means of the internet. At present the TSSTP Unit is implementing two projects for dissemination of PHARE project results. This activity will take a better advantage of today's communication technologies and ensure the management of the acquired knowledge through preservation and user-friendly access and retrieval of the project results. The paper provides an outline of the TSSTP Unit relevant knowledge preservation initiative, a description

4{sup th} Annual workshop proceedings of the collaborative project ''Redox phenomena controlling systems'' (7{sup th} EC FP CP RECOSY)

Energy Technology Data Exchange (ETDEWEB)

Altmaier, Marcus; Kienzler, Bernhard; Duro, Lara; Grive, Mireia; Montoya, Vanessa (eds.)

2012-07-01

The EURATOM 7{sup th} EC Framework Program Collaborative Project REdox phenomena Controlling SYstems (RECOSY) started in April 2008 and extends over 4 years. Although redox is not a new geochemical issue, different questions are still not resolved. For this reason, main objectives of RECOSY project are a) the sound understanding of redox phenomena controlling the long-term release/retention of radionuclides in nuclear waste disposal, b) providing tools to apply the result to Performance Assessment/Safety Case, c) training of next generation and d) documentation and communication of the results. To this aim, the project set up a consortium of 32 Beneficiaries/Contractors and 6 Associated Groups. The consortium includes key European Research Institutes, Universities, National Waste Management Agencies and SMEs, from 13 EURATOM signatory states, Russia, Japan, Korea, USA and one European Joint Research Centre. The ReCosy concept is innovative in the scientific approach to the redox phenomena. It includes i) advanced analytical tools, ii) investigations of processes responsible for redox control (thermodynamically and kinetically controlled processes, surface reactions and microbial processes,..), iii) provision of required data on redox controlling processes, and iv) response to disturbances in disposal systems. The work program is structured along six RTD workpackages (WP1-6). They cover near-field and far field aspects as well as all relevant host-rocks considered in Europe. In WP1, the scientific state-of-the-art and its application to Performance Assessment/Safety Case is documented and regularly updated. WP2 focuses on development of redox determination methods. WP3 focuses on redox response of defined and near-natural systems. WP4 studies the redox reactions of radionuclides. WP5 focuses on Redox processes in radionuclide transport and WP6 deals with redox reactions affecting the spent fuel source-term. Specific workpackages on knowledge management, education

International workshop on cold neutron sources

Energy Technology Data Exchange (ETDEWEB)

Russell, G.J.; West, C.D. (comps.) (Los Alamos National Lab., NM (United States))

1991-08-01

The first meeting devoted to cold neutron sources was held at the Los Alamos National Laboratory on March 5--8, 1990. Cosponsored by Los Alamos and Oak Ridge National Laboratories, the meeting was organized as an International Workshop on Cold Neutron Sources and brought together experts in the field of cold-neutron-source design for reactors and spallation sources. Eighty-four people from seven countries attended. Because the meeting was the first of its kind in over forty years, much time was spent acquainting participants with past and planned activities at reactor and spallation facilities worldwide. As a result, the meeting had more of a conference flavor than one of a workshop. The general topics covered at the workshop included: Criteria for cold source design; neutronic predictions and performance; energy deposition and removal; engineering design, fabrication, and operation; material properties; radiation damage; instrumentation; safety; existing cold sources; and future cold sources.

International workshop on cold neutron sources

International Nuclear Information System (INIS)

Russell, G.J.; West, C.D.

1991-08-01

The first meeting devoted to cold neutron sources was held at the Los Alamos National Laboratory on March 5--8, 1990. Cosponsored by Los Alamos and Oak Ridge National Laboratories, the meeting was organized as an International Workshop on Cold Neutron Sources and brought together experts in the field of cold-neutron-source design for reactors and spallation sources. Eighty-four people from seven countries attended. Because the meeting was the first of its kind in over forty years, much time was spent acquainting participants with past and planned activities at reactor and spallation facilities worldwide. As a result, the meeting had more of a conference flavor than one of a workshop. The general topics covered at the workshop included: Criteria for cold source design; neutronic predictions and performance; energy deposition and removal; engineering design, fabrication, and operation; material properties; radiation damage; instrumentation; safety; existing cold sources; and future cold sources

MODELS AND METHODS OF SAFETY-ORIENTED PROJECT MANAGEMENT OF DEVELOPMENT OF COMPLEX SYSTEMS: METHODOLOGICAL APPROACH

Directory of Open Access Journals (Sweden)

Олег Богданович ЗАЧКО

2016-03-01

Full Text Available The methods and models of safety-oriented project management of the development of complex systems are proposed resulting from the convergence of existing approaches in project management in contrast to the mechanism of value-oriented management. A cognitive model of safety oriented project management of the development of complex systems is developed, which provides a synergistic effect that is to move the system from the original (pre condition in an optimal one from the viewpoint of life safety - post-project state. The approach of assessment the project complexity is proposed, which consists in taking into account the seasonal component of a time characteristic of life cycles of complex organizational and technical systems with occupancy. This enabled to take into account the seasonal component in simulation models of life cycle of the product operation in complex organizational and technical system, modeling the critical points of operation of systems with occupancy, which forms a new methodology for safety-oriented management of projects, programs and portfolios of projects with the formalization of the elements of complexity.

Environmental Management Science Program Workshop

Energy Technology Data Exchange (ETDEWEB)

None

1998-07-01

This program summary book is a compendium of project summaries submitted by principal investigators in the Environmental Management Science Program and Environmental Management/Energy Research Pilot Collaborative Research Program (Wolf-Broido Program). These summaries provide information about the most recent project activities and accomplishments. All projects will be represented at the workshop poster sessions, so you will have an opportunity to meet with the researchers. The projects will be presented in the same order at the poster session as they are presented in this summary book. Detailed questions about an individual project may be directed to the investigators involved.

Original Research Does an educational workshop have an impact ...

African Journals Online (AJOL)

Studies have shown that knowledgeable caregivers are likely to exhibit high ... By definition, workshops are educational interventions aimed at giving ..... story - maternal perceptions of safety advice and information: a qualitative approach.

Implementing an interprofessional patient safety learning initiative: insights from participants, project leads and steering committee members.

Science.gov (United States)

Jeffs, Lianne; Abramovich, Ilona Alex; Hayes, Chris; Smith, Orla; Tregunno, Deborah; Chan, Wai-Hin; Reeves, Scott

2013-11-01

Effective teamwork and interprofessional collaboration are vital for healthcare quality and safety; however, challenges persist in creating interprofessional teamwork and resilient professional teams. A study was undertaken to delineate perceptions of individuals involved with the implementation of an interprofessional patient safety competency-based intervention and intervention participants. The study employed a qualitative study design that triangulated data from interviews with six steering committee members and five members of the project team who developed and monitored the intervention and six focus groups with clinical team members who participated in the intervention and implemented local patient safety projects within a large teaching hospital in Canada. Our study findings reveal that healthcare professionals and support staff acquired patient safety competencies in an interprofessional context that can result in improved patient and work flow processes. However, key challenges exist including managing projects amidst competing priorities, lacking physician engagement and sustaining projects. Our findings point to leaders to provide opportunities for healthcare teams to engage in interprofessional teamwork and patient safety projects to improve quality of patient care. Further research efforts should examine the sustainability of interprofessional safety projects and how leaders can more fully engage the participation of all professions, specifically physicians.

Grid and Entrepreneurship Workshop

CERN Multimedia

2006-01-01

The CERN openlab is organising a special workshop about Grid opportunities for entrepreneurship. This one-day event will provide an overview of what is involved in spin-off technology, with a special reference to the context of computing and data Grids. Lectures by experienced entrepreneurs will introduce the key concepts of entrepreneurship and review, in particular, the industrial potential of EGEE (the EU co-funded Enabling Grids for E-sciencE project, led by CERN). Case studies will be given by CEOs of European start-ups already active in the Grid and computing cluster area, and regional experts will provide an overview of efforts in several European regions to stimulate entrepreneurship. This workshop is designed to encourage students and researchers involved or interested in Grid technology to consider the entrepreneurial opportunities that this technology may create in the coming years. This workshop is organized as part of the CERN openlab student programme, which is co-sponsored by CERN, HP, ...

How to communicate safety? Some reflections from European project studies

International Nuclear Information System (INIS)

Richardson, Philip; Galson, Daniel

2009-12-01

Attempts to site geological disposal facilities for radioactive waste - and associated public reactions - indicate that communicating safety and demonstrating safety are very different things. The three different approaches to stakeholder engagement undertaken in the context of the PAMINA, ARGONA and CIP projects have provided valuable insights into how risk communication processes and tools can be improved. The approaches used in these projects all involve the participation of interested stakeholders in identifying concerns and issues, which are then examined in a co-operative fashion between stakeholders and developers acting in partnership. Such approaches offer avenues for dialogue and confidence building where such channels were previously not well developed, Full results from the projects will be available in late 2009 for PAMINA and ARGONA and in early 2010 for CIP. The comments and interim insights outlined here will be developed further and incorporated in the overall project outputs, and help inform developing European policy in this area. It is already clear, however, that the approaches used in these projects offer great promise in helping to develop the trust in the institutions and organisations involved that is essential in gaining support and acceptance for the waste management activities now underway across Europe

2. Annual Workshop Proceedings of the Integrated Project 'Fundamental Processes of Radionuclide Migration' - 6. EC FP IP FUNMIG

International Nuclear Information System (INIS)

Buckau, Gunnar; Kienzler, Bernhard; Duro, Lara; Montoya, Vanessa

2007-06-01

This Workshop combined various types of activities and meetings with the following objectives: Inform about the scientific progress; Inform about the administrative status; Inform/agree upon forthcoming reporting; Discuss various topics of interest (for example, various aspects of Integration ); Inform about and discuss training; Agree upon the forthcoming work program. Emphasis was on scientific-technical topics with administrative issues kept to the minimum necessary. The proceedings are divided into the following sections: Research, Technology and Development Components activity overviews, with summaries where scientific highlights were presented. These were: RTDC1: Influence of inorganic carbon of Ni(II) and Co(II) sorption on Na-illite and Opalinus clay; Adsorption of humics to iron oxides and its effects on ion adsorption. RTDC2: Sorption of Uranium onto granite and altered material from Aespoe HRL; Sorption and reduction of uranyl by Fe(II) minerals; Mobility of uranium during the reductive dissolution of iron oxides by sulfide; U(VI/IV) adsorption mechanism on biotite surfaces and clarification of the influence of redox reactions on the U(VI) adsorption. RTDC3: Interlayer hydration H 2 O 'paradigm' (mono-porosity model); Porosity/mineral distribution characterisation (mm-cm scale), GIS system for CO x 'transport pertinent' data sets. A topical session was held around subjects associated with performance assessment/the Safety Case, especially relevant for geologic disposal in crystalline rock. The topics were: Role of biogeochemical processes on radionuclide migration; Characterization of geochemical conditions in crystalline rock/ Process identification and verification by real system analysis; Fluid flow system characterization in crystalline rock (Effects of the heterogeneity and up-scaling). Individual Scientific and Technical Contributions, containing reviewed scientific and technical manuscripts: European OBservatory for Long-term Governance on

2. Annual Workshop Proceedings of the Integrated Project 'Fundamental Processes of Radionuclide Migration' - 6. EC FP IP FUNMIG

Energy Technology Data Exchange (ETDEWEB)

Buckau, Gunnar; Kienzler, Bernhard [FZK - Inst. fuer Nukleare Entsorgung, Ka rlsruhe (Germany); Duro, Lara; Montoya, Vanessa [Enviros Spain S.L., Barcelona (Spai n)

2007-06-15

This Workshop combined various types of activities and meetings with the following objectives: Inform about the scientific progress; Inform about the administrative status; Inform/agree upon forthcoming reporting; Discuss various topics of interest (for example, various aspects of Integration ); Inform about and discuss training; Agree upon the forthcoming work program. Emphasis was on scientific-technical topics with administrative issues kept to the minimum necessary. The proceedings are divided into the following sections: Research, Technology and Development Components activity overviews, with summaries where scientific highlights were presented. These were: RTDC1: Influence of inorganic carbon of Ni(II) and Co(II) sorption on Na-illite and Opalinus clay; Adsorption of humics to iron oxides and its effects on ion adsorption. RTDC2: Sorption of Uranium onto granite and altered material from Aespoe HRL; Sorption and reduction of uranyl by Fe(II) minerals; Mobility of uranium during the reductive dissolution of iron oxides by sulfide; U(VI/IV) adsorption mechanism on biotite surfaces and clarification of the influence of redox reactions on the U(VI) adsorption. RTDC3: Interlayer hydration H{sub 2}O 'paradigm' (mono-porosity model); Porosity/mineral distribution characterisation (mm-cm scale), GIS system for CO{sub x} 'transport pertinent' data sets. A topical session was held around subjects associated with performance assessment/the Safety Case, especially relevant for geologic disposal in crystalline rock. The topics were: Role of biogeochemical processes on radionuclide migration; Characterization of geochemical conditions in crystalline rock/ Process identification and verification by real system analysis; Fluid flow system characterization in crystalline rock (Effects of the heterogeneity and up-scaling). Individual Scientific and Technical Contributions, containing reviewed scientific and technical manuscripts: European OBservatory for Long-term Governance

Report of the Danish national workshop

DEFF Research Database (Denmark)

Esbjerg, Lars; Grunert, Klaus G.

2003-01-01

product groups in the workshop. Invitees from the fruit business were either unable to attend or not interested. Also, there were no participants from the retail trade. It was positive that several of the invitees unable to attend complained that they had prior engagements they had to keep...... for food safety and for making quality food products available to consumers as well as the role consumers play, both in relation to their willingness-to-pay for food safety and their ability to handle food products safely....

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

International Nuclear Information System (INIS)

Duckwitz, Noel

2011-01-01

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

Ferrocyanide safety project ferrocyanide aging studies. Final report

International Nuclear Information System (INIS)

Lilga, M.A.; Hallen, R.T.; Alderson, E.V.

1996-06-01

This final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In the laboratory, such mixtures can be made to undergo uncontrolled or explosive reactions by heating dry reagents to over 200 degrees C. In 1987, an Environmental Impact Statement (EIS), published by the U.S. Department of Energy (DOE), Final Environmental Impact Statement, Disposal of Hanford Defense High-Level Transuranic and Tank Waste, Hanford Site, Richland, Washington, included an environmental impact analysis of potential explosions involving ferrocyanide-nitrate mixtures. The EIS postulated that an explosion could occur during mechanical retrieval of saltcake or sludge from a ferrocyanide waste tank, and concluded that this worst-case accident could create enough energy to release radioactive material to the atmosphere through ventilation openings, exposing persons offsite to a short-term radiation dose of approximately 200 mrem. Later, in a separate study (1990), the General Accounting Office postulated a worst-case accident of one to two orders of magnitude greater than that postulated in the DOE EIS. The uncertainties regarding the safety envelope of the Hanford Site ferrocyanide waste tanks led to the declaration of the Ferrocyanide Unreviewed Safety Question (USQ) in October 1990

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

International Nuclear Information System (INIS)

Conner, J.C.

1994-01-01

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

The art of regression modeling in road safety

CERN Document Server

Hauer, Ezra

2015-01-01

This unique book explains how to fashion useful regression models from commonly available data to erect models essential for evidence-based road safety management and research. Composed from techniques and best practices presented over many years of lectures and workshops, The Art of Regression Modeling in Road Safety illustrates that fruitful modeling cannot be done without substantive knowledge about the modeled phenomenon. Class-tested in courses and workshops across North America, the book is ideal for professionals, researchers, university professors, and graduate students with an interest in, or responsibilities related to, road safety. This book also: · Presents for the first time a powerful analytical tool for road safety researchers and practitioners · Includes problems and solutions in each chapter as well as data and spreadsheets for running models and PowerPoint presentation slides · Features pedagogy well-suited for graduate courses and workshops including problems, solutions, and PowerPoint p...

Evaluation of the Geothermal Public Power Utility Workshops in California

Energy Technology Data Exchange (ETDEWEB)

Farhar, B. C.

2004-10-01

The federal government devotes significant resources to educating consumers and businesses about geothermal energy. Yet little evidence exists for defining the kinds of information needed by the various audiences with specialized needs. This paper presents the results of an evaluation of the Geothermal Municipal Utility Workshops that presented information on geothermal energy to utility resource planners at customer-owned utilities in California. The workshops were sponsored by the Western Area Power Administration and the U.S. Department of Energy's GeoPowering the West Program and were intended to qualitatively assess the information needs of municipal utilities relative to geothermal energy and get feedback for future workshops. The utility workshop participants found the geothermal workshops to be useful and effective for their purposes. An important insight from the workshops is that utilities need considerable lead-time to plan a geothermal project. They need to know whether it is better to own a project or to purchase geothermal electricity from another nonutility owner. California customer-owned utilities say they do not need to generate more electricity to meet demand, but they do need to provide more electricity from renewable resources to meet the requirements of the state's Renewable Portfolio Standard.

Building the Human Vaccines Project: strategic management recommendations and summary report of the 15-16 July 2014 business workshop.

Science.gov (United States)

Schenkelberg, Theodore; Kieny, Marie-Paule; Bianco, A E; Koff, Wayne C

2015-05-01

The Human Vaccines Project is a bold new initiative, with the goal of solving the principal scientific problem impeding vaccine development for infectious diseases and cancers: the generation of specific, broad, potent and durable immune responses in humans. In the July 2014 workshop, 20 leaders from the public and private sectors came together to give input on strategic business issues for the creation of the Human Vaccines Project. Participants recommended the Project to be established as a nonprofit public-private partnership, structured as a global R&D consortium closely engaged with industrial partners, and located/affiliated with one or more major academic centers conducting vaccine R&D. If successful, participants concluded that the Project could greatly accelerate the development of new and improved vaccines, with the potential to transform disease prevention in the 21st century.

International Criticality Safety Benchmark Evaluation Project (ICSBEP) - ICSBEP 2015 Handbook

International Nuclear Information System (INIS)

Bess, John D.

2015-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy (DOE). The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Nuclear Energy Agency (NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirements and placement. Many of the specifications are also useful for nuclear data testing. Example calculations are presented; however, these calculations do not constitute a validation of the codes or cross-section data. The evaluated criticality safety benchmark data are given in nine volumes. These volumes span approximately 69000 pages and contain 567 evaluations with benchmark specifications for 4874 critical, near-critical or subcritical configurations, 31 criticality alarm placement/shielding configurations with multiple dose points for each, and 207 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. New to the handbook are benchmark specifications for neutron activation foil and thermoluminescent dosimeter measurements performed at the SILENE critical assembly in Valduc, France as part of a joint venture in 2010 between the US DOE and the French Alternative Energies and Atomic Energy Commission (CEA). A photograph of this experiment is shown on the front cover. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these

Overview of the NKS/RAK-1 project 'Strategies for reactor safety' and linkages to piping reliability studies

International Nuclear Information System (INIS)

Andersson, Kjell

1997-01-01

The NKS/RAK-1 project forms part of a four-year research program (1994-97) in the Nordic countries. The general objective of NKS/RAK-1 project is to explore strategies for reactor safety: to investigate and evaluate the safety work, to increase realism and reliability of safety analysis; and to increase the safety of nuclear installations in selected areas. The project has done extensive interview work at utilities and authorities, and analysed a number of case studies. Brief highlights and overviews of the sub-projects are presented in this paper

Executive summary. Summary of the workshop sessions

International Nuclear Information System (INIS)

2012-01-01

The workshop played a great role in sharing the current state-of-the art on the PSA (Probabilistic Safety Assessment) of new and advanced reactors, and points of interest among member countries. The major concern expressed by the participants included passive safety system reliability, digital system reliability, new and advanced reactors-specific risk assessment methodology and relevant computational tool, and safety-security interface, etc). Main findings obtained from the workshop are as follows. For new reactors, the role of PSA is more important and more formalized comparing with exiting reactors. The PSAs are being used in the design of new reactors for purposes such as balance between accident prevention and mitigation features of the design, demonstration of safety, identification of design vulnerabilities and improvements, and comparison with the risk of existing plants, etc. For advanced reactors, the role of PSA is also being regarded as an essential tool for safety improvement and comparison of reactor designs at the conceptual or preliminary stages, but their practical use is at the early stage to gain the insights of risk into these reactors. This is due to the fact that the use of PSA for advanced reactors is mainly focused on identifying the PSA issues for designer and regulatory bodies, and developing the relevant methodologies and tools. Better guidance and peer review process on the PSA of new and advanced reactors was identified by both industry and regulatory as an important aspect

1993 DOE technical standards managers workshop: Proceedings

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

This workshop is focused on the benefits of the DOE technical standards program, which is focused toward the preferred use of non-Government standards for DOE activities and the development of DOE technical standards when non-Government standards are not available or are inappropriate. One goal of the program is to replace redundant site-specific standards with more universally accepted documents that have been scrutinized by experts. This replacement is discussed at the workshop along with the problems encountered and solutions found. The workshop provided an opportunity for geographically dispersed people to meet and advance their standards knowledge and efforts to support the program. Safety issues have been the driving force behind the program to date. Several companies offer products and services that support the development, processing, and retrieval of standards. This document mostly comprise vugraphs.

5th Total System Performance Assessment Workshop

International Nuclear Information System (INIS)

Hwang, Yong Soo; Lee, Youn Myoung; Kang, Chul Hyung; Lee, Sung Ho

2009-07-01

Research items on safety assessment of high-level waste repository have been proposed by external invited experts outside KAERI and discussed extensively during the annual 5th performance assessment workshop prepared by safety assessment group in KAERI. This could be useful to set up R and D plans necessary for the next phase of mid- and long-term reaserch area regarding the safety assessment of high-level waste repository. Through the research and the presentation, HLW-related research and development area including such specific research items as current status of HLW safety assessment research, current requirement for the licensing of the repository system, priority on research area, data base building for the safety assessment, source-term modeling as well as safety case, among many others, have been discussed and summarized

Asian-American Communications: In-School Staff Workshops, 1991-92. Final Evaluation Report. OREA Report.

Science.gov (United States)

Zhang, Zenin

The In-School Staff Workshops project run by Asian-American Communications was evaluated in its fourth year. The project provided various workshops for staff on Asian American and Asian cultures, intercultural communications, and strategies for helping Asian American students adjust to their new social and educational environments. The project…

Proceedings of the workshop on reliability data collection

International Nuclear Information System (INIS)

1999-01-01

The main purpose of the Workshop was to provide a forum for exchanging information and experience on Reliability Data Collection and analysis to support Living Probabilistic Safety Assessments (LPSA). The Workshop is divided into four sessions which titles are: Session 1: Reliability Data - Database Systems (3 papers), Session 2: Reliability Data Collection for PSA (5 papers), Session 3: NPP Data Collection (3 papers), Session 4: Reliability Data Assessment (Part 1: General - 2 papers; Part 2: CCF - 2 papers; Part 3: Reactor Protection Systems / External Event Data - 2 papers; Part 4: Human Errors - 2 papers)

No 2943. Project of law relative to nuclear transparency and safety

International Nuclear Information System (INIS)

2006-03-01

This project of law comprises 5 titles dealing with: 1 - general dispositions: definition and scope of nuclear safety, security, radiation protection, operators liability, facilities in concern; 2 - the high nuclear safety authority: role and duties; 3 - public information in the domain of nuclear safety and radiation protection: information right of the public, local information commissions, high committee for nuclear safety transparency and information; 4 - basic nuclear facilities and transport of radioactive materials: applicable rules, police controls and measures, penal dispositions (investigations, sanctions); 5 - miscellaneous dispositions: changes made with respect to previous legislative texts. (J.S.)

Two related narratives: learning from an evaluation of a short coaching workshop and a pilot coaching project

Directory of Open Access Journals (Sweden)

Keith Jones

2015-11-01

Full Text Available Background and context: A key role of the district’s Nursing Midwifery Practice and Workforce Unit is to build capability in the nursing and midwifery workforce. In this paper I reflect on the experience of my team following attendance at a two-day Coaching for Performance workshop and the impact this had on developing coaching skills for nurse managers and nurse unit managers in South Eastern Sydney Local Health District. Aims: To highlight how engaging in critical reflection enabled the unit team to identify gaps in the transfer of coaching skills learned from the two-day workshop to everyday management practices. The pilot project to embed coaching into management practices is the result of the team’s reflection. The method, findings and implications for coaching practices for nurse managers and nurse unit managers are described in detail. Findings: Using Gibbs’ model of reflection, the unit team reflected on its collective experiences following attendance at the workshop. This led to the development of a pilot coaching project called Embedding Coaching into Practice for nurse managers and nurse unit managers, which enabled the transfer of coaching skills learned to everyday management practices. The pilot project used a ‘coaching the coach’ approach, with structured follow-up at the managers’ places of work. This had a positive impact on the development of coaching skills and managers were able to use these skills with confidence to enable their staff to develop problem-solving skills. Conclusions: This paper highlights how using a validated tool for reflection can lead to positive change. ‘Coaching the coach’ can support transfer of coaching skills learned into everyday practices, which has a positive impact on work performance for nurse managers, nurse unit managers and their staff. It supports the practice development principle that lifelong learning can influence effective workplace cultures and have a positive impact on

The Halden Reactor Project Workshop on Studies of Operator Performance During Night Shift's

International Nuclear Information System (INIS)

Morisseau, Dolores S.; Braarud, Per Oeyvind; Collier, Steve; Droeivoldsmo, Asgeir; Larsen, Marit; Lirvall, Peter

1996-01-01

A workshop on Studies of Operator Performance during Nights Shifts was organised in Halden, February 27-28, 1996. The purpose of the workshop was to discuss and make recommendations on specific needs for the study of operator cognitive performance at night and identify the relevant research issues for which Halden could provide resolution. The workshop began with presentations by several invited speakers with expertise in studies of shift work and was then divided into three working groups that discussed the following issues in parallel: (1) Lines of Research to Be Pursued; (2) Methods and Measures to Be Used in Research on Cognitive Performance at Nights; and (3) Products of the Research on Operator Performance at Night. Each group produced specific recommendations that were summarised by the group's facilitator in a joint session of the workshop. This report summarises the presentation of the invited speakers, and the discussions and recommendations of the individual working groups. (author)

Summary of the Workshop on Neutron Cross Section Covariances

International Nuclear Information System (INIS)

Smith, Donald L.

2008-01-01

A Workshop on Neutron Cross Section Covariances was held from June 24-27, 2008, in Port Jefferson, New York. This Workshop was organized by the National Nuclear Data Center, Brookhaven National Laboratory, to provide a forum for reporting on the status of the growing field of neutron cross section covariances for applications and for discussing future directions of the work in this field. The Workshop focused on the following four major topical areas: covariance methodology, recent covariance evaluations, covariance applications, and user perspectives. Attention was given to the entire spectrum of neutron cross section covariance concerns ranging from light nuclei to the actinides, and from the thermal energy region to 20 MeV. The papers presented at this conference explored topics ranging from fundamental nuclear physics concerns to very specific applications in advanced reactor design and nuclear criticality safety. This paper provides a summary of this workshop. Brief comments on the highlights of each Workshop contribution are provided. In addition, a perspective on the achievements and shortcomings of the Workshop as well as on the future direction of research in this field is offered

Safety Assessment Methodologies and Their Application in Development of Near Surface Waste Disposal Facilities--ASAM Project

International Nuclear Information System (INIS)

Batandjieva, B.; Metcalf, P.

2003-01-01

Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years

Refrigeration and air-conditioning technology workshop

Energy Technology Data Exchange (ETDEWEB)

Lewis, P. J.; Counce, D. M. [eds.

1993-01-01

The Alternative Fluorocarbon Environmental Acceptability Study (AFEAS), a consortium of fluorocarbon manufacturers, and the US Department of Energy (DOE) are collaborating on a project to evaluate the energy use and global warming impacts of CFC alternatives. The goal of this project is to identify technologies that could replace the use of CFCs in refrigeration, heating, and air-conditioning equipment; to evaluate the direct impacts of chemical emissions on global warming; and to compile accurate estimates of energy use and, indirect CO{sub 2} emissions of substitute technologies. The first phase of this work focused on alternatives that could be commercialized before the year 2000. The second phase of the project is examining not-in-kind and next-generation technologies that could be developed to replace CFCs, HCFCs, and HFCs over a longer period. As part of this effort, Oak Ridge National Laboratory held a workshop on June 23--25, 1993. The preliminary agenda covered a broad range of alternative technologies and at least one speaker was invited to make a brief presentation at the workshop on each technology. Some of the invited speakers were unable to participate, and in a few cases other experts could not be identified. As a result, those technologies were not represented at the workshop. Each speaker was asked to prepare a five to seven page paper addressing six key issues concerning the technology he/she is developing. These points are listed in the sidebar. Each expert also spoke for 20 to 25 minutes at the workshop and answered questions from the other participants concerning the presentation and area of expertise. The primary goal of the presentations and discussions was to identify the developmental state of the technology and to obtain comparable data on system efficiencies. Individual papers are indexed separately.

DIKU-LASMEA Workshop on Computer Vision, Copenhagen, March, 2009

DEFF Research Database (Denmark)

Fihl, Preben

This report will cover the participation in the DIKU-LASMEA Workshop on Computer Vision held at the department of computer science, University of Copenhagen, in March 2009. The report will give a concise description of the topics presented at the workshop, and briefly discuss how the work relates...... to the HERMES project and human motion and action recognition....

Technology Requirements For In Situ Decommissioning Workshop Report

International Nuclear Information System (INIS)

Jannik, T.; Lee, P.; Gladden, J.; Langton, C.; Serrato, M.; Urland, C.; Reynolds, E.

2009-01-01

In recognition of the increasing attention being focused on In Situ Decommissioning (ISD or entombment) as an acceptable and beneficial decommissioning end state, the Department of Energy's (DOE) Office of Environmental Management (EM) is developing guidance for the implementation of ISD of excess facilities within the DOE complex. Consistent with the overarching DOE goals for increased personnel and environmental safety, reduced technical uncertainties and risks, and overall gains in efficiencies and effectiveness, EM's Office of Deactivation and Decommissioning and Facility Engineering (EM-23) initiated efforts to identify the technical barriers and technology development needs for the optimal implementation of ISD. Savannah River National Laboratory (SRNL), as the EM Corporate Laboratory, conducted an ISD Technology Needs Workshop to identify the technology needs at DOE sites. The overall goal of the workshop was to gain a full understanding of the specific ISD technical challenges, the technologies available, and those needing development. The ISD Workshop was held December 9-10, 2008 in Aiken, SC. Experienced decommissioning operations personnel from Richland Operations Office (RL), Idaho National Laboratory (INL) and Savannah River Site (SRS) along with scientists and engineers specific expertise were assembled to identify incremental and 'game changing' solutions to ISD technology challenges. The workshop and follow-up activities yielded 14 technology needs statements and the recommendation that EM-23 prioritize and pursue the following specific technology development and deployment actions. For each action, the recommended technology acquisition mechanisms (competitive solicitation (CS) or direct funding (TCR)) are provided. Activities that are time critical for ISD projects, or require unique capabilities that reside in the DOE Laboratory system will be funded directly to those institutions. Activities that have longer lead times and where the private

Interactive Forms of Open Scientific and Educational Workshop

Directory of Open Access Journals (Sweden)

Naumova Galina Alekseevna

2014-12-01

Full Text Available The article discusses the innovative chain of the Russian economy which consists of three stages: “Idea” (academic science, “Technology” (applied science, and “Production”. The authors describe the innovative system of Russia in terms of infrastructure devices, the functioning of the financial system and human resources. Special attention is paid to the problem of staff training for the innovation economy in Russia. The authors propose the use of scientific and educational public workshop as a form of interactive courses in training staff for the “economy of knowledge”. The article describes the experience of holding open seminars at the Department of Innovation Studies of Volgograd State University. The members of project teams of scientific and Interdisciplinary Innovative Design educational center take part in these discussions. Four scenarios of public workshops are suggested. The first one refers to the joint research work of students, undergraduates and graduate students. The activity includes the presentation of research projects, collective work of students in the creation of business models, innovative projects, debates in the format of a talk show on current topics in the field of innovation and business. The participants also discuss the latest technological and scientific advances in the field of innovations with practical application in business by means of webinars. The second scenario implies an open workshop in the form of presentation of research results based on the technology of group project-based learning as an interactive method which is widely used in the leading universities of the world, and is the organization of educational process in the form of implementation of group projects, from the stage of their development to practical implementation. Team work (“brainstorming” open workshop consists in the creation of business models, innovative projects based on the use of techniques of prominent

Performance assessment, participative processes and value judgements. Report from the first RISCOM II workshop

Energy Technology Data Exchange (ETDEWEB)

Andersson, Kjell [Karinta-Konsult, Taeby (Sweden); Lilja, Christina [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)] (eds.)

2001-12-01

This workshop was the first one in a series of three workshops within the RISCOM-II project. The aim was to gather the status of the project as a starting point to enhance discussions between project participants and with a number of invited participants. The seminar also included two presentations from the OECD/NEA on NEA work related to stake holder participation, as well as the EC Concerted Action COWAM. Discussions were held in direct connection to the talks and in special sessions. The first day of the workshop entitled Value judgements,risk communication and performance assessment was moderated by Magnus Westerlind (SKI), the RISCOM-II coordinator. The second day was entitled Case studies exploring implications for the practical development of risk communication and was moderated by Anna Littleboy, UK Nirex Ltd. The workshop was opened by Thierry Devries, EDF. He welcomed the participants to Paris and gave some remarks about the French nuclear waste management situation and highlighted the significant French and EDF participation in RISCOM-II. He meant that the project should have possibilities to enhance transparency in nuclear waste programmes and noted that the new concept of stretching, introduced by RISCOM, is already is use. In the following the talks given at the workshop and the discussion that took place are summarized. Appendix 3 gives a brief overview of the RISCOM-II project.

Performance assessment, participative processes and value judgements. Report from the first RISCOM II workshop

International Nuclear Information System (INIS)

Andersson, Kjell; Lilja, Christina

2001-12-01

This workshop was the first one in a series of three workshops within the RISCOM-II project. The aim was to gather the status of the project as a starting point to enhance discussions between project participants and with a number of invited participants. The seminar also included two presentations from the OECD/NEA on NEA work related to stake holder participation, as well as the EC Concerted Action COWAM. Discussions were held in direct connection to the talks and in special sessions. The first day of the workshop entitled Value judgements,risk communication and performance assessment was moderated by Magnus Westerlind (SKI), the RISCOM-II coordinator. The second day was entitled Case studies exploring implications for the practical development of risk communication and was moderated by Anna Littleboy, UK Nirex Ltd. The workshop was opened by Thierry Devries, EDF. He welcomed the participants to Paris and gave some remarks about the French nuclear waste management situation and highlighted the significant French and EDF participation in RISCOM-II. He meant that the project should have possibilities to enhance transparency in nuclear waste programmes and noted that the new concept of stretching, introduced by RISCOM, is already is use. In the following the talks given at the workshop and the discussion that took place are summarized. Appendix 3 gives a brief overview of the RISCOM-II project

Proceedings for air quality management programs: A workshop on lessons learned

Energy Technology Data Exchange (ETDEWEB)

Streit, G.E. [comp.

1993-06-01

The coordinators of this project at Los Alamos National Laboratory and the Instituto Mexicano del Petroleo proposed a workshop to bring together an international group of experts to present both the lessons of history and the current practices in air quality management around the world. The workshop would also serve as a forum for presenting the accomplishments and plans of this project and for receiving comments from the assembled group. The workshop was favored with an outstanding set of speakers who represented a broad spectrum of experience. Their papers are presented in this volume. The total attendance was forty-four (see List of Participants) with representation from numerous interested Mexican institutions. Individual reports are processed separately for the database.

Proceedings for air quality management programs: A workshop on lessons learned

International Nuclear Information System (INIS)

Streit, G.E.

1993-06-01

The coordinators of this project at Los Alamos National Laboratory and the Instituto Mexicano del Petroleo proposed a workshop to bring together an international group of experts to present both the lessons of history and the current practices in air quality management around the world. The workshop would also serve as a forum for presenting the accomplishments and plans of this project and for receiving comments from the assembled group. The workshop was favored with an outstanding set of speakers who represented a broad spectrum of experience. Their papers are presented in this volume. The total attendance was forty-four (see List of Participants) with representation from numerous interested Mexican institutions. Individual reports are processed separately for the database

Project SAFE. Update of the SFR-1 safety assessment. Phase 1

International Nuclear Information System (INIS)

Andersson, Johan; Riggare, P.; Skagius, K.

1998-10-01

SFR-1 is a facility for disposal of low-level radioactive operational waste from the nuclear power plants in Sweden. Low-level radioactive waste from industry, medicine, and research is also disposed in SFR-1. The facility is situated in bedrock beneath the Baltic Sea, 1 km off the coast near the Forsmark nuclear power plant. SFR-1 was built between the years 1983 and 1988. An assessment of the long-term performance of the facility was included in the vast documentation that was a part of the application for an operational license. The assessment was presented in the form of a final safety report. In the operational licence for SFR-1 it is stated that renewed safety assessments should be carried out at least each ten years. In order to meet this demand SKB has launched a special project, SAFE (Safety Assessment of Final Disposal of Operational Radioactive Waste). The aim of the project is to update the safety analysis and to prepare a safety report that will be presented to the Swedish authorities not later than year 2000. Project SAFE is divided into three phases. The first phase is a prestudy, and the results of the prestudy are given in this report. The aim of the prestudy is to identify issues where additional studies would improve the basis for the updated safety analysis as well as to suggest how these studies should be carried out. The work has been divided into six different topics, namely the inventory, the near field, the far field, the biosphere, radionuclide transport calculations and scenarios. For each topic the former safety reports and regulatory reviews are scrutinised and needs for additional work is identified. The evaluations are given in appendices covering the respective topics. The main report is a summary of the appendices with a more stringent description of the repository system and the processes that are of interest and therefore should be addressed in an updated safety assessment. However, it should be pointed out that one of the

Proceedings of the 5th US/German Workshop on Salt Repository Research Design and Operation

Energy Technology Data Exchange (ETDEWEB)

Hansen, Francis D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Leigh, Christi [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Walter [Karlsruhe Inst. of Technology (KIT) (Germany); Bollingerfehr, Wilhelm [DBE Technology, Peine (Germany); Von Berlepsche, Thilo [DBE Technology, Peine (Germany)

2015-01-01

The 5th US/German Workshop on Salt Repository Research, Design, and Operation was held in Santa Fe New Mexico September 8-10, 2014. The forty seven registered participants were equally divided between the United States (US) and Germany, with one participant from The Netherlands. The agenda for the 2014 workshop was under development immediately upon finishing the 4th Workshop. Ongoing, fundamental topics such as thermomechanical behavior of salt, plugging and sealing, the safety case, and performance assessment continue to advance the basis for disposal of heat-generating nuclear waste in salt formations. The utility of a salt underground research laboratory (URL) remains an intriguing concept engendering discussion of testing protocol. By far the most interest in this years’ workshop pertained to operational safety. Given events at the Waste Isolation Pilot Plant (WIPP), this discussion took on a new sense of relevance and urgency.

Recent Workshops

CERN Multimedia

Wickens, F. J.

Since the previous edition of ATLAS e-news, the NIKHEF Institute in Amsterdam has hosted not just one but two workshops related to ATLAS TDAQ activities. The first in October was dedicated to the Detector Control System (DCS). Just three institutes, CERN, NIKHEF and St Petersburg, provide the effort for the central DCS services, but each ATLAS sub-detector provides effort for their own controls. Some 30 people attended, including representatives for all of the ATLAS sub-detectors, representatives of the institutes working on the central services and the project leader of JCOP, which brings together common aspects of detector controls across the LHC experiments. During the three-day workshop the common components were discussed, and each sub-detector described their experiences and plans for their future systems. Whilst many of the components to be used are standard commercial components, a key custom item for ATLAS is the ELMB (Embedded Local Monitor Board). Prototypes for this have now been extensively test...

Environmental radioactive monitoring, evaluation and protection in luminous workshops of a factory

International Nuclear Information System (INIS)

Dai Hanbin; Xiang Ming; Tan Jianzu

2009-01-01

Fluorescent technique is often used to display instrumental indicator in the dark environment. Luminous workshops of a factory smear and depict the glassware by means of fluorescent power with adulterated radioactive matter. Because of adulterated radioactive matters such as 226 Ra, 40 K emit alpha-ray,beta-ray and gamma-ray, while they decay spontaneously, and high dose or cumulative radiation can damage human body in different degrees. Therefore, any radioactive damage to human body caused by over-safety dose should be prevented strictly during the working. To ensure health and safety of working staff in luminous workshop and the public, it is necessary to regularly have radioactive monitoring and evaluation to luminous workshop and its surrounding environment. Through the environment radioactive monitoring, the authors analyze its environmental radioactive level,and try to find out the possible problems so as to propose some protective measures for personal health. (authors)

Air quality management and planning system for Guangzhou. Report from workshop 1, 1998

International Nuclear Information System (INIS)

Larssen, Steinar

1999-02-01

The report is proceedings from Workshop no. 1, 1998 of the Sino-Norwegian co-operation project ''Guangzhou Air Quality Management and Planning System''. The project studies pollution emissions generally and from coal, vehicle and energy activities, dispersion modelling, monitoring, exposure, health damage assessment, material damage assessment, vegetation, control options, baseline scenario development, cost benefit analysis, pollution control management and policy instruments and air pollution forecasting. A forth workshop is planned. There are several reports from the various project activities

Canadian Site Visit and Workshop - Summary and International Perspective

International Nuclear Information System (INIS)

2003-01-01

The third workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by Natural Resources Canada (NRCan) for three days in Ottawa, following a one-day visit of the Port Hope area which included meetings with community representatives and project managers and a tour of low-level waste management facilities. The Ottawa workshop examined social concerns regarding radioactive waste management: what the concerns are, how they are identified, and how they can be addressed. Sixty-nine people attended the workshop from fourteen countries and forty-five organizations. They ranged from representatives of municipal governments, non-governmental organizations and private citizens to government policy makers, regulators, implementers, consultants and university, social and media researchers. The participants included stakeholders in large-scale industrial projects (both nuclear and nonnuclear) and stakeholders directly affected by nuclear projects. About one half came from FSC member organisations; the remainders were Canadian stakeholders. The workshop was structured with five half-day sessions. The opening half-day described Canadian policy and the regulatory environment for radioactive waste management and the two central case studies for the workshop: the Port Hope Area Initiative and the Nuclear Fuel Waste Act. Three sessions addressed the topics 'What are the social concerns?', 'How to address social concerns?' and 'Development opportunities for communities'. Each of the sessions began with plenary presentations by five stakeholders. These 'stakeholder voices' were followed by roundtable discussions. The participants were divided into eight tables, each including a mix of Canadian and other attendees. Each table discussed a set of pre-defined questions under the direction of a facilitator/Rapporteur. The discussions from each round table were reported in a follow-up plenary. The final half-day of the workshop was

Proceedings of Wireless Technology in the Electric Power Industry Workshop

International Nuclear Information System (INIS)

2001-01-01

A one-day workshop was conducted at EPRI Charlotte to identify technology issues related to wireless technology in nuclear power plants. The meeting concluded with a roundtable discussion to determine what projects could be conducted to address opportunities and gaps in this technology; the three projects recommended for further investigation were a risk analysis, development of a technology strategy, and development of guidelines for reliable implementation of wireless technologies. The Proceedings CD includes workshop presentations in PowerPoint format. The presentations cover the following topics: (1) Wireless Project at TXU: Integration of Voice, Data, and Video; (2) Radio Upgrade Project at Public Service Electric and Gas Company (PSE and G) of New Jersey; and (3) Operational Experience with Wireless Communication at Nuclear Plants

Legacy data sharing to improve drug safety assessment: the eTOX project

DEFF Research Database (Denmark)

Sanz, Ferran; Pognan, François; Steger-Hartmann, Thomas

2017-01-01

The sharing of legacy preclinical safety data among pharmaceutical companies and its integration with other information sources offers unprecedented opportunities to improve the early assessment of drug safety. Here, we discuss the experience of the eTOX project, which was established through...

Breckinridge Project, initial effort. Report VII, Volume 4. Safety and health plan

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

The Safety and Health Plan recognizes the potential hazards associated with the Project and has been developed specifically to respond to these risks in a positive manner. Prevention, the primary objective of the Plan, starts with building safety controls into the process design and continues through engineering, construction, start-up, and operation of the Project facilities and equipment. Compliance with applicable federal, state, and local health and safety laws, regulations, and codes throughout all Project phases is required and assured. The Plan requires that each major Project phase be thoroughly reviewed and analyzed to determine that those provisions required to assure the safety and health of all employees and the public, and to prevent property and equipment losses, have been provided. The Plan requires followup on those items or situations where corrective action needs were identified to assure that the action was taken and is effective. Emphasis is placed on loss prevention. Exhibit 1 provides a breakdown of Ashland Synthetic Fuels, Inc.'s (ASFI's) Loss Prevention Program. The Plan recognizes that the varied nature of the work is such as to require the services of skilled, trained, and responsible personnel who are aware of the hazards and know that the work can be done safely, if done correctly. Good operating practice is likewise safe operating practice. Training is provided to familiarize personnel with good operational practice, the general sequence of activities, reporting requirements, and above all, the concept that each step in the operating procedures must be successfully concluded before the following step can be safely initiated. The Plan provides for periodic review and evaluation of all safety and loss prevention activities at the plant and departmental levels.

The SISIFO project: Seismic Safety at High Schools

Science.gov (United States)

Peruzza, Laura; Barnaba, Carla; Bragato, Pier Luigi; Dusi, Alberto; Grimaz, Stefano; Malisan, Petra; Saraò, Angela; Mucciarelli, Marco

2014-05-01

For many years, the Italian scientific community has faced the problem of the reduction of earthquake risk using innovative educational techniques. Recent earthquakes in Italy and around the world have clearly demonstrated that seismic codes alone are not able to guarantee an effective mitigation of risk. After the tragic events of San Giuliano di Puglia (2002), where an earthquake killed 26 school children, special attention was paid in Italy to the seismic safety of schools, but mainly with respect to structural aspects. Little attention has been devoted to the possible and even significant damage to non-structural elements (collapse of ceilings, tipping of cabinets and shelving, obstruction of escape routes, etc..). Students and teachers trained on these aspects may lead to a very effective preventive vigilance. Since 2002, the project EDURISK (www.edurisk.it) proposed educational tools and training programs for schools, at primary and middle levels. More recently, a nationwide campaign aimed to adults (www.iononrischio.it) was launched with the extensive support of civil protection volounteers. There was a gap for high schools, and Project SISIFO was designed to fill this void and in particular for those schools with technical/scientific curricula. SISIFO (https://sites.google.com/site/ogssisifo/) is a multidisciplinary initiative, aimed at the diffusion of scientific culture for achieving seismic safety in schools, replicable and can be structured in training the next several years. The students, helped by their teachers and by experts from scientific institutions, followed a course on specialized training on earthquake safety. The trial began in North-East Italy, with a combination of hands-on activities for the measurement of earthquakes with low-cost instruments and lectures with experts in various disciplines, accompanied by specifically designed teaching materials, both on paper and digital format. We intend to raise teachers and students knowledge of the

Infrastructure design & road safety : OECD Workshop B3 (Infrastructure design and road safety) for CEE's and NIS held on 15th-18th November 1994, Prague (Czech Republic). Part 1: Summaries, conclusions and recommendations, and statements from Central and Eastern European countries.

NARCIS (Netherlands)

2012-01-01

The workshop 'Infrastructure design and road safety ' was one of the initiatives which the OECO Steering Committee for Road Transport Research developed with the aim of exchanging information in the road transport sector, in order to respond to the urgent needs expressed by Central and Eastern

Delivery of workshops on mobility monitoring in small to medium-sized communities.

Science.gov (United States)

2009-11-01

This report summarizes the delivery and outcome of a series of workshops conducted in 13 cities across the : state on performing mobility monitoring in small to medium-sized communities. The workshops served as : implementation for research project 0...

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

Science.gov (United States)

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

2011-01-01

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

Specifications of the International Atomic Energy Agency's international project on safety assessment driven radioactive waste management solutions

International Nuclear Information System (INIS)

Ghannadi, M.; Asgharizadeh, F.; Assadi, M. R.

2008-01-01

Radioactive waste is produced in the generation of nuclear power and the production and use of radioactive materials in the industry, research, and medicine. The nuclear waste management facilities need to perform a safety assessment in order to ensure the safety of a facility. Nuclear safety assessment is a structured and systematic way of examining a proposed facility, process, operation and activity. In nuclear waste management point of view, safety assessment is a process which is used to evaluate the safety of radioactive waste management and disposal facilities. In this regard the International Atomic Energy Agency is planed to implement an international project with cooperation of some member states. The Safety Assessment Driving Radioactive Waste Management Solutions Project is an international programme of work to examine international approaches to safety assessment in aspects of p redisposal r adioactive waste management, including waste conditioning and storage. This study is described the rationale, common aspects, scope, objectives, work plan and anticipated outcomes of the project with refer to International Atomic Energy Agency's documents, such as International Atomic Energy Agency's Safety Standards, as well as the Safety Assessment Driving Radioactive Waste Management Solutions project reports

The International Criticality Safety Benchmark Evaluation Project (ICSBEP)

International Nuclear Information System (INIS)

Briggs, J.B.

2003-01-01

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in 1992 by the United States Department of Energy. The ICSBEP became an official activity of the Organisation for Economic Cooperation and Development (OECD) - Nuclear Energy Agency (NEA) in 1995. Representatives from the United States, United Kingdom, France, Japan, the Russian Federation, Hungary, Republic of Korea, Slovenia, Yugoslavia, Kazakhstan, Israel, Spain, and Brazil are now participating. The purpose of the ICSBEP is to identify, evaluate, verify, and formally document a comprehensive and internationally peer-reviewed set of criticality safety benchmark data. The work of the ICSBEP is published as an OECD handbook entitled 'International Handbook of Evaluated Criticality Safety Benchmark Experiments.' The 2003 Edition of the Handbook contains benchmark model specifications for 3070 critical or subcritical configurations that are intended for validating computer codes that calculate effective neutron multiplication and for testing basic nuclear data. (author)

Report of international workshop on technical elements for aviation safety; Koku anzensei kojo no tame no gijutsu kadai ni kansuru kokusai kaigi wo kaisaishite

Energy Technology Data Exchange (ETDEWEB)

Terada, H. [National Aerospace Laboratory, Tokyo (Japan)

1999-06-05

The international workshop on technical elements for aviation safety was opened in Tokyo on March 15-17, 1999 with 75 domestic and overseas participants, and 18 reports. On aircraft operation, report was made on the research of a practical visual sense supporting equipment for cockpits to reduce workload of crew at takeoff and landing, and improve a safety. On human factor, report was made on the managers` recognition of their responsibility on safety in Titanic accident. On aircraft passenger cabin safety and emergency escape, discussion was made on the order of priority of 30 factors effective for improving a survival rate in crush accidents, and report was made on current R & D of flame retardant interior materials with less toxicity for passenger cabins. On aircraft body structure, report was made on the research on growth and propagation of fatigue cracks by more than 10{sup 8} cycle loading, and the simulation of complex loading to estimate residual lives of body structure. (NEDO)

Current practice and recommendations in UK epilepsy monitoring units. Report of a national survey and workshop.

Science.gov (United States)

Hamandi, Khalid; Beniczky, Sandor; Diehl, Beate; Kandler, Rosalind H; Pressler, Ronit M; Sen, Arjune; Solomon, Juliet; Walker, Matthew C; Bagary, Manny

2017-08-01

Inpatient video-EEG monitoring (VEM) is an important investigation in patients with seizures or blackouts, and in the pre-surgical workup of patients with epilepsy. There has been an expansion in the number of Epilepsy Monitoring Units (EMU) in the UK offering VEM with a necessary increase in attention on quality and safety. Previous surveys have shown variation across centres on issues including consent and patient monitoring. In an effort to bring together healthcare professionals in the UK managing patients on EMU, we conducted an online survey of current VEM practice and held a one-day workshop convened under the auspices of the British Chapter of the ILAE. The survey and workshop aimed to cover all aspects of VEM, including pre-admission, consent procedures, patient safety, drug reduction and reinstatement, seizure management, staffing levels, ictal testing and good data recording practice. This paper reports on the findings of the survey, the workshop presentations and workshop discussions. 32 centres took part in the survey and there were representatives from 22 centres at the workshop. There was variation in protocols, procedures and consent processes between units, and levels of observation of monitored patients. Nevertheless, the workshop discussion found broad areas of agreement on points. A survey and workshop of UK epilepsy monitoring units found that some variability in practice is inevitable due to different local arrangements and patient groups under investigation. However, there were areas of clear consensus particularly in relation to consent and patient safety that can be applied to most units and form a basis for setting minimum standards. Copyright © 2017 British Epilepsy Association. Published by Elsevier Ltd. All rights reserved.

Summary of the Workshop

International Nuclear Information System (INIS)

Myers, S; Zimmermann, F

2012-01-01

The summary session of the LHC Performance Workshop in Chamonix, 6-10 February 2012, synthesized one week of presentations and intense discussions on the near-, medium- and long-term strategy for the LHC and LHC upgrades. In particular, Chamonix’12 discussed the lessons from 2011, the strategy, beam energy and beam parameters for 2012, the planning for the Long Shutdown no. 1 (LS1), the measures and schemes for improving or maintaining the machine availability at higher beam energy, the injector performance and injector upgrade schedule, the HL-LHC project as well as possible additional or future LHC upgrades like LHeC and HELHC. Key workshop themes included the risk associated with 4 TeV beam energy in 2012, the beam energy after LS1, the turnaround time, the physics goal and optimized running schedule for 2012, the achievements and plans for Pb-Pb and p-Pb collisions, beam-beam effects, electron-cloud phenomena and UFOs. We report the proposals for decisions which have emerged at the Chamonix’12 workshop. (author)

Summary of the Workshop

Energy Technology Data Exchange (ETDEWEB)

Myers, S; Zimmermann, F [European Organization for Nuclear Research, Geneva (Switzerland)

2012-07-01

The summary session of the LHC Performance Workshop in Chamonix, 6-10 February 2012, synthesized one week of presentations and intense discussions on the near-, medium- and long-term strategy for the LHC and LHC upgrades. In particular, Chamonix’12 discussed the lessons from 2011, the strategy, beam energy and beam parameters for 2012, the planning for the Long Shutdown no. 1 (LS1), the measures and schemes for improving or maintaining the machine availability at higher beam energy, the injector performance and injector upgrade schedule, the HL-LHC project as well as possible additional or future LHC upgrades like LHeC and HELHC. Key workshop themes included the risk associated with 4 TeV beam energy in 2012, the beam energy after LS1, the turnaround time, the physics goal and optimized running schedule for 2012, the achievements and plans for Pb-Pb and p-Pb collisions, beam-beam effects, electron-cloud phenomena and UFOs. We report the proposals for decisions which have emerged at the Chamonix’12 workshop. (author)

Visit safety

CERN Document Server

2012-01-01

Experiment areas, offices, workshops: it is possible to have co-workers or friends visit these places.     You already know about the official visits service, the VIP office, and professional visits. But do you know about the safety instruction GSI-OHS1, “Visits on the CERN site”? This is a mandatory General Safety Instruction that was created to assist you in ensuring safety for all your visits, whatever their nature—especially those that are non-official. Questions? The HSE Unit will be happy to answer them. Write to safety-general@cern.ch.   The HSE Unit

USEPAM Project: The State of Progress

DEFF Research Database (Denmark)

Lund, Søren

The paper represents the introductory speech at the 2nd regional workshop of the USEPAM project in Phnom Penh March 2005. It gives a review of the project's activities and achievements, and an introduction to the objectives, structure and programme of the workshop...

The Nordic nuclear safety program 1994-1997. Project handbook

International Nuclear Information System (INIS)

1997-06-01

This is a new revision of the handbook for administrators of the Nordic reactor safety program NKS. The most important administrative functions in project management are described, which should secure a uniform management approach in all the projects. The description of the organizational scheme of the NKS and distribution of responsibilities is followed by examples of various administrative routines and document forms. In the annex the names and addresses of the staff involved in administration of the NKS program are listed. (EG)

Air quality management and planning system for Guangzhou. Report from workshop 1, 1998

Energy Technology Data Exchange (ETDEWEB)

Larssen, Steinar

1999-02-01

The report is proceedings from Workshop no. 1, 1998 of the Sino-Norwegian co-operation project ''Guangzhou Air Quality Management and Planning System''. The project studies pollution emissions generally and from coal, vehicle and energy activities, dispersion modelling, monitoring, exposure, health damage assessment, material damage assessment, vegetation, control options, baseline scenario development, cost benefit analysis, pollution control management and policy instruments and air pollution forecasting. A forth workshop is planned. There are several reports from the various project activities.

Culinary Workshop as a Competitive Advantage of Tourism Industry in the South Karelia Region of Finland

OpenAIRE

Lvov, Anatoly

2014-01-01

Culinary workshop is a new form of modern hospitality industry, which combines modern knowledge in tourism industry with culinary tourism. This project is based on the interest of the consumer and his desire to learn something new, get and experience gastronomy traditions through travelling for culinary workshop. Mission of this project is to convey to the consumer new knowledge, new skill, new interest, opportunities in life through culinary art. Culinary workshops will be descri...

Game-Coding Workshops in New Zealand Public Libraries: Evaluation of a Pilot Project

Science.gov (United States)

Bolstad, Rachel

2016-01-01

This report evaluates a game coding workshop offered to young people and adults in seven public libraries round New Zealand. Participants were taken step by step through the process of creating their own simple 2D videogame, learning the basics of coding, computational thinking, and digital game design. The workshops were free and drew 426 people…

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

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

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

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

International Nuclear Information System (INIS)

1994-02-01

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

76 FR 51041 - Hemoglobin Standards and Maintaining Adequate Iron Stores in Blood Donors; Public Workshop

Science.gov (United States)

2011-08-17

...] Hemoglobin Standards and Maintaining Adequate Iron Stores in Blood Donors; Public Workshop AGENCY: Food and... Donors.'' The purpose of this public workshop is to discuss blood donor hemoglobin and hematocrit qualification standards in the United States, its impact on donor safety and blood availability, and potential...