International consensus on safety principles

International Nuclear Information System (INIS)

Warnecke, E.

1993-01-01

The International Atomic Energy Agency (IAEA) has been regularly requested by its Member States to provide evidence that radioactive waste can be managed safely and to help demonstrate a harmonization of approach at the international level by providing safety documents. In response, IAEA established a special series of safety documents devoted to radioactive waste management. These documents will be elaborated within the Radioactive Waste Safety Standards (RADWASS) programme [1,2] which covers all aspects of radioactive waste management. The RADWASS programme develops a series of international consensus documents on all parts of the safe management of radioactive waste, including disposal. The purpose of the RADWASS programme is to (i) document existing international consensus in the approaches and methodologies for safe radioactive waste management, (ii) create a mechanism to establish consensus where it does not exist and (iii) provide Member States with a comprehensive series of internationally agreed upon documents to complement national standards and criteria. This paper describes the RADWASS programme, and covers the structure, implementation plans and status of documents under preparation

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-06-01

economic conditions. Valuable time and effort in implementing these programmes could be saved by increasing the exchange of information on the engineering solutions and implementation of the safety modifications among the countries in Eastern Europe. Mechanisms for the exchange of information should be strengthened. Consistency in both the probabilistic and deterministic approaches is desired and could be reached through systematic information exchanges among the Eastern Europe countries. The IAEA could provide one useful forum for these exchanges. Continued international assistance is also appropriate in this area. A high level of interest in nuclear safety in Eastern Europe was evidenced by the countries dedicated efforts to complete effective keynote papers to guide discussions in the conference. Discussions over the week of these papers among the participants provided new insights into solutions for safety issues that remain in these countries. These papers and the presentations will be placed on the internet by each of the Eastern European countries and the IAEA will link these to the web site of the IAEA nuclear safety department for easy reference Refs, figs, tabs

49 CFR 659.27 - Internal safety and security reviews.

Science.gov (United States)

2010-10-01

... 49 Transportation 7 2010-10-01 2010-10-01 false Internal safety and security reviews. 659.27... State Oversight Agency § 659.27 Internal safety and security reviews. (a) The oversight agency shall... safety and security reviews in its system safety program plan. (b) The internal safety and security...

International cooperation for operating safety

International Nuclear Information System (INIS)

Dupuis, M.C.

1989-03-01

The international-cooperation organization in nuclear safety domain is discussed. The nuclear energy Direction Committee is helped by the Security Committee for Nuclear Power Plants in the cooperation between security organizations of member countries and in the safety and nuclear activity regulations. The importance of the cooperation between experts in human being and engine problems is underlined. The applied methods, exchange activities and activity analysis, and the cooperation of the Nuclear Energy Agency and international organizations is analysed [fr

Simulation research to enhance patient safety and outcomes: recommendations of the Simnovate Patient Safety Domain Group

OpenAIRE

Pucher, PH; Tamblyn, R; Boorman, D; Dixon-Woods, Mary Margaret; Donaldson, L; Draycott, T; Forster, A; Nadkarni, V; Power, C; Sevdalis, N; Aggarwal, R

2017-01-01

The use of simulation-based training has established itself in healthcare but its implementation has been varied and mostly limited to technical and non-technical skills training. This article discusses the possibilities of the use of simulation as part of an overarching approach to improving patient safety, and represents the views of the Simnovate Patient Safety Domain Group, an international multidisciplinary expert group dedicated to the improvement of patient safety. The application and ...

Standards: An international framework for nuclear safety

International Nuclear Information System (INIS)

Versteeg, J.

2000-01-01

The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

International Nuclear Safety Center (INSC) database

International Nuclear Information System (INIS)

Sofu, T.; Ley, H.; Turski, R.B.

1997-01-01

As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

Towards an international regime on radiation and nuclear safety

International Nuclear Information System (INIS)

Gonzalez, A.J.

2000-01-01

The 1990s have seen the de facto emergence of what might be called an 'international regime on nuclear and radiation safety'. It may be construed to encompass three key elements: legally binding international undertakings among States; globally agreed international safety standards; and provisions for facilitating the application of those standards. While nuclear and radiation safety are national responsibilities, governments have long been interested in formulating harmonised approaches to radiation and nuclear safety. A principal mechanism for achieving harmonisation has been the establishment of internationally agreed safety standards and the promotion of their global application. The development of nuclear and radiation safety standards is a statutory function of the IAEA, which is unique in the United Nations system. The IAEA Statute expressly authorises the Agency 'to establish standards of safety' and 'to provide for the application of these standards'. As the following articles and supplement in this edition of the IAEA Bulletin point out, facilitating international conventions; developing safety standards; and providing mechanisms for their application are high priorities for the IAEA. (author)

Establishment of an international nuclear safety body

International Nuclear Information System (INIS)

Rosen, M.

1983-01-01

During the past year there has been increasing interest in the establishment of new international mechanisms for developing a more uniform approach to nuclear safety. The tasks, organizational nature and affiliation, composition and structure, and financial support of an international nuclear safety body are discussed in the article

Use of commercial grade item dedication to reduce procurement costs

International Nuclear Information System (INIS)

Rosch, F.

1995-01-01

In the mid-1980s, the Nuclear Regulatory Industry (NRC) began inspecting utility practices of procuring and dedicating commercial grade items intended for plant safety-related applications. As a result of the industry efforts to address NRC concerns, nuclear utilities have enhanced existing programs and procedures for dedication of commercial grade items. Though these programs were originally enhanced to meet NRC concerns, utilities have discovered that the dedication of commercial grade items can also reduce overall procurement costs. This paper will discuss the enhancement of utility dedication programs and demonstrates how utilities have utilized them to reduce procurement costs

Nuclear power performance and safety. V.3. Safety and international co-operation

International Nuclear Information System (INIS)

1988-01-01

The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. This objective was accomplished through presentation and discussion of about 200 papers at the Conference. Almost 500 participants and observers from 40 countries and 12 organizations discussed three major questions which were posed as the focus of this Conference: (1) What are the current trends and major issues with regard to performance and safety of nuclear power, the nuclear fuel cycle and radioactive waste management? (2) What steps are being taken or need to be taken to resolve outstanding issues in order to improve the performance of nuclear power with assured safety? (3) What performance objectives and achievements can be anticipated for the 1990s? All presentations of this Conference were divided into six volumes. This is Volume 3 which is devoted to the problems of safety and international cooperation. All presentations of Volume 3 were divided into four sessions as follows: the need for safety in nuclear power programmes (4 papers); international cooperation in nuclear safety (6 papers); technical aspects in plant safety (7 papers); approaches to safety (3 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

Editors note, and Dedication

Directory of Open Access Journals (Sweden)

Laura Mugnai

2011-12-01

Full Text Available This Supplement to volume 50 of Phytopathologia Mediterranea contains original, peer reviewed research papers, prepared from presentations at the 7th International Workshop on Grapevine Trunk Diseases (IWGTD. This Workshop was held in Santa Cruz, Chile, 17–21 January 2010, and was organized by the International Council on Grapevine Trunk Diseases (ICGTD.  Publication of this Supplement has been financially assisted by the International Society for Plant Pathology (ISPP.This Supplementary Issue of Phytopathologia Mediterranea is dedicated to the memory of Dr Luigi Chiarappa, the founder and inspiration of the ICGTD.  

IAEA establishes International Seismic Safety Centre

International Nuclear Information System (INIS)

2008-01-01

Full text: The IAEA today officially inaugurated an international centre to coordinate efforts for protecting nuclear installations against the effects of earthquakes. The International Seismic Safety Centre (ISSC), which has been established within the IAEA's Department of Nuclear Safety and Security, will serve as a focal point on seismic safety for nuclear installations worldwide. ISSC will assist countries on the assessment of seismic hazards of nuclear facilities to mitigate the consequences of strong earthquakes. 'With safety as our first priority, it is vital that we pool all expert knowledge available worldwide to assist nuclear operators and regulators to be well prepared for coping with major seismic events,' said Antonio Godoy, Acting Head of the IAEA's Engineering Safety Section and leader of the ISSC. 'The creation of the ISSC represents the culmination of three decades of the IAEA's active and recognized involvement in this matter through the development of an updated set of safety standards and the assistance to Member States for their application.' To further seismic safety at nuclear installations worldwide, the ISSC will: - Promote knowledge sharing among the international community in order to avoid or mitigate the consequences of extreme seismic events on nuclear installations; - Support countries through advisory services and training courses; and - Enhance seismic safety by utilizing experience gained from previous seismic events in member states. The centre is supported by a scientific committee of high-level experts from academic, industrial and nuclear safety authorities that will advise the ISSC on implementation of its programme. Experts have been nominated from seven specialized areas, including geology and tectonics, seismology, seismic hazard, geotechnical engineering, structural engineering, equipment, and seismic risk. Japan and the United States have both contributed initial funds for creation of the centre, which will be based at

Safety Design Criteria of Indian Sodium Cooled Fast Reactors

International Nuclear Information System (INIS)

Pillai, P.; Chellapandi, P.; Chetal, S.C.; Vasudeva Rao, P.R.

2013-01-01

• Important feedback has been gained through the design and safety review of PFBR. • The safety criteria document prepared by AERB and IGCAR would provide important input to prepare the dedicated document for the Sodium cooled Fast Reactors at the national and international level. • A common approach with regard to safety, among countries pursuing fast reactor program, is desirable. • Sharing knowledge and experimental facilities on collaborative basis. • Evolution of strong safety criteria – fundamental to assure safety

Spanish Nuclear Safety Research under International Frameworks

Energy Technology Data Exchange (ETDEWEB)

Herranz, L. E.; Reventos, F.; Ahnert, C.; Jimenez, G.; Queral, C.; Verdu, G.; Miro, R.; Gallardo, S.

2013-10-01

The Nuclear Safety research requires a wide international collaboration of several involved groups. In this sense this paper pretends to show several examples of the Nuclear Safety research under international frameworks that is being performed in different Universities and Research Institutions like CIEMAT, Universitat Politecnica de Catalunya (UPC), Universidad Politecnica de Madrid (UPM) and Universitat Politenica de Valencia (UPV). (Author)

International Cooperation in the Field of International Space Station (ISS) Payload Safety

Science.gov (United States)

Heimann, Timothy; Larsen, Axel M.; Rose, Summer; Sgobba, Tommaso

2005-01-01

In the frame of the International Space Station (ISS) Program cooperation, in 1998, the European Space Agency (ESA) approached the National Aeronautics and Space Administration (NASA) with the unique concept of a Payload Safety Review Panel (PSRP) "franchise" based at the European Space Technology Center (ESTEC), where the panel would be capable of autonomously reviewing flight hardware for safety. This paper will recount the course of an ambitious idea as it progressed into a fully functional reality. It will show how a panel initially conceived at NASA to serve a national programme has evolved into an international safety cooperation asset. The PSRP established at NASA began reviewing ISS payloads approximately in late 1994 or early 1995 as an expansion of the pre-existing Shuttle Program PSRP. This paper briefly describes the fundamental Shuttle safety process and the establishment of the safety requirements for payloads intending to use the Space Transportation System and International Space Station (ISS). The paper will also offer some historical statistics about the experiments that completed the payload safety process for Shuttle and ISS. The paper 1 then presents the background of ISS agreements and international treaties that had to be taken into account when establishing the ESA PSRP. The detailed franchising model will be expounded upon, followed by an outline of the cooperation charter approved by the NASA Associate Administrator, Office of Space Flight, and ESA Director of Manned Spaceflight and Microgravity. The resulting ESA PSRP implementation and its success statistics to date will then be addressed. Additionally the paper presents the ongoing developments with the Japan Aerospace Exploration Agency. The discussion will conclude with ideas for future developments, such to achieve a fully integrated international system of payload safety panels for ISS.

A proposal for an international convention on radiation safety

International Nuclear Information System (INIS)

Ahmed, J.U.

1998-01-01

One century has passed since harmful effects of radiation on living tissues were recognized. Organized efforts to reduce radiation hazards began in early 1920s. Major efforts by the ICRP since 1928, aided by ICRU, greatly helped in formulating principles, policies and guidance for radiation protection. The WHO formally recognized ICRP in 1956 and began implementing ICRP recommendations and guidance throughout the world. The IAEA, after it took office in 1957, began to establish or adopt standards of safety based on ICRP recommendations and provide for application of these standards in the field of atomic energy. Later on, other pertinent international organizations joined IAEA in establishing the Basic Safety Standards on radiation safety. The IAEA has issued, until now, nearly couple of hundred safety related documents on radiation safety and waste management. However, in spite of all such international efforts for three quarter of a century, there has been no effective universal control in radiation safety. Problems exist at the user, national, international and manufacturers and suppliers levels. Other problems are management of spent sources and smuggling of sources across international borders. Although, radiation and radionuclides are used by all countries of the world, regulatory and technical control measures in many countries are either lacking or inadequate. The recommendations and technical guidance provided by the international organizations are only advisory and carry no mandatory force to oblige countries to apply them. Member States approve IAEA safety standards and guides at the technical meetings and General Conference, but many of them do not apply these. An International Convention is, therefore, essential to establish international instrument to ensure universal application of radiation safety. (author)

Towards an International Approach to Nuclear Safety

International Nuclear Information System (INIS)

Tomihiro Taniguchi

2006-01-01

This document presents in a series of transparencies the different activities of the IAEA: Introduction of International Atomic Energy Agency, Changing world, Changing Technology, Changing Global Security, Developing Innovative Nuclear Energy Systems, Global Nuclear Safety Regime, IAEA Safety Standards: Hierarchy - Global Reference for Striving for Excellence, IAEA Safety Reviews and Services: Integrated Safety Approach, Global Knowledge Network - Asian Nuclear Safety Network, Safety Issues and Challenges, Synergy between Safety and Security, Recent Developments: Safety and Security of Radioactive Sources, Convention on Physical Protection of Nuclear Material (CPPNM), Incident and Emergency Preparedness and Response, Holistic Approach for Safety and Security, Sustainable Development. (J.S.)

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

Internal safety review team at Comanche Peak SES

Energy Technology Data Exchange (ETDEWEB)

Davis, D [Comanche Peak Steam Electric Staion, Texas Utilities, TX (United States)

1997-09-01

The presentations describes the following issues: levels of defense in depth; internal safety review organizations; methods used to perform safety assessment; safety committee review; quality verification; root cause analysis; human performance program; industry operating experience.

International Cooperation in the Field of International Space Station (ISS) Payload Safety

Science.gov (United States)

Grayson, C.; Sgobba, T.; Larsen, A.; Rose, S.; Heimann, T.; Ciancone, M.; Mulhern, V.

2005-12-01

In the frame of the International Space Station (ISS) Program cooperation, in 1998 the European Space Agency (ESA) approached the National Aeronautics and Space Administration (NASA) with the unique concept of a Payload Safety Review Panel (PSRP) "franchise" based at the European Space Technology Center (ESTEC), where the panel would be capable of autonomously reviewing flight hardware for safety. This paper will recount the course of an ambitious idea as it progressed into a fully functional reality. It will show how a panel initially conceived at NASA to serve a national programme has evolved into an international safety cooperation asset. The PSRP established at NASA began reviewing ISS payloads approximately in late 1994 or early 1995 as an expansion of the pre- existing Shuttle Program PSRP. This paper briefly describes the fundamental Shuttle safety process and the establishment of the safety requirements for payloads intending to use the Space Transportation System and ISS. The paper will also offer some historical statistics about the experiments that completed the payload safety process for Shuttle and ISS. The paper then presents the background of ISS agreements and international treaties that had to be considered when establishing the ESA PSRP. The paper will expound upon the detailed franchising model, followed by an outline of the cooperation charter approved by the NASA Associate Administrator, Office of Space Flight, and ESA Director of Manned Spaceflight and Microgravity. The paper will then address the resulting ESA PSRP implementation and its success statistics to date. Additionally, the paper presents ongoing developments with the Japan Aerospace Exploration Agency (JAXA). The discussion will conclude with ideas for future developments, such to achieve a fully integrated international system of payload safety panels for ISS.

Introduction to 'International Handbook of Criticality Safety Benchmark Experiments'

International Nuclear Information System (INIS)

Komuro, Yuichi

1998-01-01

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

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

2013-01-01

The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

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

International Nuclear Information System (INIS)

2014-01-01

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

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

International Nuclear Information System (INIS)

2016-01-01

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

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

International Nuclear Information System (INIS)

2015-01-01

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

Radiation protection and safety of radiation sources international basic safety standards

CERN Document Server

International Atomic Energy Agency. Vienna

2014-01-01

The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

Safety of radioactive waste management. Proceedings of an international conference

International Nuclear Information System (INIS)

2000-01-01

The principal objective of the Conference was to enable members of the scientific community and representatives of facilities which produce radioactive waste, of bodies responsible for radioactive waste management, of nuclear regulatory bodies and of public interest groups, among others, to engage in an open dialogue. The open dialogue which took place may, by providing policy and decision makers with a basis for political action, prove to be an important step in the search for the international consensus so essential in the area of radioactive waste management. The relevant policies and activities of the IAEA, the European Commission, the OECD Nuclear Energy Agency and the World Health Organization were presented. The evolution, under the aegis of the IAEA, of a de facto international radiation and nuclear safety regime was noted. In the area of radioactive waste safety, this regime consists of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the body of international waste safety standards established by the IAEA and other international organizations, and the IAEA's mechanisms for providing for the application of those standards. The topics covered by the Conference were: Current international co-operative efforts; Recommendations from the International Commission on Radiological Protection; Recommendations from the International Nuclear Safety Advisory Group; Conclusions and recommendations of the International Symposium on the Restoration of Environments with Radioactive Residues; Siting of radioactive waste management facilities; Participation of interested parties; Legislative and general radiation safety aspects; Removal of material from regulatory control (exclusion, exemption and clearance); Predisposal management (dilution, recycling, transmutation, etc.); Near surface disposal; Residues from the mining and processing of radioactive ores; Long term institutional control; Geological disposal

The safety relief valve handbook design and use of process safety valves to ASME and International codes and standards

CERN Document Server

Hellemans, Marc

2009-01-01

The Safety Valve Handbook is a professional reference for design, process, instrumentation, plant and maintenance engineers who work with fluid flow and transportation systems in the process industries, which covers the chemical, oil and gas, water, paper and pulp, food and bio products and energy sectors. It meets the need of engineers who have responsibilities for specifying, installing, inspecting or maintaining safety valves and flow control systems. It will also be an important reference for process safety and loss prevention engineers, environmental engineers, and plant and process designers who need to understand the operation of safety valves in a wider equipment or plant design context. . No other publication is dedicated to safety valves or to the extensive codes and standards that govern their installation and use. A single source means users save time in searching for specific information about safety valves. . The Safety Valve Handbook contains all of the vital technical and standards informat...

International Safety Regulation and Standards for Space Travel and Commerce

Science.gov (United States)

Pelton, J. N.; Jakhu, R.

The evolution of air travel has led to the adoption of the 1944 Chicago Convention that created the International Civil Aviation Organization (ICAO), headquartered in Montreal, Canada, and the propagation of aviation safety standards. Today, ICAO standardizes and harmonizes commercial air safety worldwide. Space travel and space safety are still at an early stage of development, and the adoption of international space safety standards and regulation still remains largely at the national level. This paper explores the international treaties and conventions that govern space travel, applications and exploration today and analyzes current efforts to create space safety standards and regulations at the national, regional and global level. Recent efforts to create a commercial space travel industry and to license commercial space ports are foreseen as means to hasten a space safety regulatory process.

New challenges for the internal safety organisation

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, Per Langå

2003-01-01

Research from several countries indicates that the internal health and safety organisation in most companies is placed in an appendix position. Introduc-tion of learning is a possibility for the development of a stronger and more ef-fective health and safety organisation. This approach has been...

International Symposium on Nuclear Safety

International Nuclear Information System (INIS)

2013-03-01

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

Approaches to nuclear safety

International Nuclear Information System (INIS)

Watkins, J.D.

1990-01-01

This article examines the factors which affect the safe operation of a nuclear power plant. Some of these are an organizational and individual dedication to safety and excellence in every aspect of plant functions, international cooperation, and advanced reactor design. These are in addition to excellence in management of nuclear plants and the training of key operations personnel. The author feels all of these are necessary to restore public confidence in nuclear power

Nuclear Safety through International Cooperation

International Nuclear Information System (INIS)

Flory, Denis

2013-01-01

The Fukushima Daiichi nuclear accident was the worst at a nuclear facility since the Chernobyl accident in 1986. It caused deep public anxiety and damaged confidence in nuclear power. Following this accident, strengthening nuclear safety standards and emergency response has become an imperative at the global level. The IAEA is leading in developing a global approach, and the IAEA Action Plan on Nuclear Safety is providing a comprehensive framework and acting as a significant driving force to identify lessons learned and to implement safety improvements. Strengthening nuclear safety is addressed through a number of measures proposed in the Action Plan including 12 main actions focusing on safety assessments in the light of the accident. Significant progress has been made in assessing safety vulnerabilities of nuclear power plants, strengthening the IAEA's peer review services, improvements in emergency preparedness and response capabilities, strengthening and maintaining capacity building, as well as widening the scope and enhancing communication and information sharing with Member States, international organizations and the public. Progress has also been made in reviewing the IAEA's safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on accident prevention, in particular severe accidents, and emergency preparedness and response.

Ukraine International cooperation in nuclear and radiation safety: public-administrative aspect

Directory of Open Access Journals (Sweden)

I. P. Krynychnay

2017-03-01

Full Text Available The article examines international cooperation of Ukraine with other States in the sphere of ensuring nuclear and radiation safety and highlights the main directions of development and improvement of nuclear and radiation safety in Ukraine based on international experience, with the aim of preventing the risks of accidents and contamination areas radiological substances. Illuminated that for more than half a century of experience in the use of nuclear energy by the international community under the auspices of the UN, IAEA and other international organizations initiated and monitored the implementation of key national and international programs on nuclear and radiation safety. Of the Convention in the field of nuclear safety and the related independent peer review, effective national regulatory infrastructures, current nuclear safety standards and policy documents, as well as mechanisms of evaluation in the framework of the IAEA constitute important prerequisites for the creation of a world community, the global regime of nuclear and radiation safety. For analysis of the state of international cooperation of Ukraine with other States in the sphere of nuclear and radiation safety, highlighted the legal substance of nuclear and radiation safety of Ukraine, which is enshrined in the domestic Law of Ukraine «On nuclear energy use and radiation safety». Considered the most relevant legal relations. It is established that, despite the current complex international instruments, existing domestic legislation on nuclear and radiation safety, partly there is a threat of emergency nuclear radiation nature, in connection with the failure of fixed rules and programs, lack of funding from the state is not always on time and in full allows you to perform fixed strategy for overcoming the consequences of radiation accidents, the prevention of the threat of environmental pollution. Found that to improve and further ensuring nuclear and radiation safety of

International conference on topical issues in nuclear safety. Contributed papers

International Nuclear Information System (INIS)

2001-01-01

The objective of the Conference was to foster the exchange of information on topical issues in nuclear safety, with the aim of consolidating an international consensus on the present status of these issues, priorities for future work, and needs for strengthening international cooperation, including the IAEA recommendations for future activities. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference: risk informed decision making, influence of external factors on safety, safety of fuel cycle facilities, safety of research reactors, and safety performance indicators

International conference on topical issues in nuclear safety. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The objective of the Conference was to foster the exchange of information on topical issues in nuclear safety, with the aim of consolidating an international consensus on the present status of these issues, priorities for future work, and needs for strengthening international cooperation, including the IAEA recommendations for future activities. This book contains concise contributed papers submitted on issues falling within the thematic scope of the Conference: risk informed decision making, influence of external factors on safety, safety of fuel cycle facilities, safety of research reactors, and safety performance indicators.

Commercial Grade Item (CGI) Dedication for Leak Detection Relays

International Nuclear Information System (INIS)

KOCH, M.R.; JOHNS, B.R.

1999-01-01

This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping and Instrumentation Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

EPR safety. Consideration of the internal and external hazards in the safety studies

International Nuclear Information System (INIS)

Gueguin, H.

2008-04-01

The author presents the main points of the Preliminary Safety Report of EDF on the EPR reactor safety. It concerns the considerations of the internal (fire, flood, explosions, pipes failures) and external (earthquakes, airplane falls, explosions, exceptional natural disasters, extreme meteorological conditions) damages. It presents how the safety report takes into account the aggression. (A.L.B.)

The nuclear power safety programme of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Rosen, M.

1981-01-01

The role of the International Atomic Energy Agency in the field of nuclear power safety is growing. In the period since the Three Mile Island accident, a significant expansion in its nuclear safety programme has taken place. To assure an acceptable safety level world-wide, new emphasis is being placed on the major effort to establish and foster the use of a comprehensive set of internationally agreed safety standards for nuclear power plants. New initiatives are in progress to intensify international co-operative safety efforts through the exchange of information on safety-related operating occurrences, and through a more open sharing of safety research results. Emergency accident assistance lends itself to international co-operation and steps are being taken to establish an emergency assistance programme so the Agency can aid in co-ordinating a timely response to provide, at short notice, help and advice in case of a nuclear power accident. There has been some strengthening of those advisory services which involve missions of international experts primarily to countries with less developed nuclear power programmes, and in conjunction with the Technical Assistance Programme there is a co-ordinated programme for developing countries, involving safety training courses and assistance aimed at promoting an effective national regulatory programme in all countries using nuclear power. This paper discusses the major features of the IAEA activities in nuclear power plant safety. An understanding of the programme and its limitations is essential to its more effective use. Additional initiatives may still be proposed, but the possibilities for international and regional co-operation to assure an adequate level of safety world-wide already exist. (author)

The international state of affairs in marine safety

International Nuclear Information System (INIS)

Benkert, W.M.

1978-01-01

The three-fold objective of marine safety is examined with emphasis on international cooperation as a means of achievement. In this respect, the recent and present activities of the Intergovernmental Maritime Consultative organization are reviewed by looking at the accomplishments and goals of several subcommittees of the Maritime Safety Committee. The United States program for commercial vessel safety is briefly discussed along with a comment on the recent Tanker Safety initiatives

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)

International survey of living PSA and safety indicators

International Nuclear Information System (INIS)

Holmberg, J.; Laakso, K.; Lehtinen, E.; Bjoere, S.

1992-01-01

The report contains an international overview of applications of living probabilistic assessment and development of operational safety indicators. Features of an ideal living PSA tool are summarized as well as a limited survey of code systems for managing a living probabilistic safety assessment (living PSA) is included. The international survey is used as an input for planning and performance of related tasks within the nordic NKS/SIK-1 project conducted in 1990-93. The research notes are distributed to the Nordic organizations involved or interested in the subject. The report includes an overview and conclusions from technical reports and articles available and presentations and discussions related to development and use of above methods for the evaluation and management of the operational safety of nuclear power plants. A large part of this material is based on material collected and discussed in connection to international specialist meetings relating to the subject

Assuring fish safety and quality in international fish trade

International Nuclear Information System (INIS)

Ababouch, Lahsen . E-mail lahsen.ababouch@fao.org

2006-01-01

International trade in fishery commodities reached US$ 58.2 billion in 2002, a 5% improvement relative to 2000 and a 45% increase over 1992 levels. Within this global trade, developing countries registered a net trade surplus of US$ 17.4 billion in 2002 and accounted for almost 50% by value and 55% of fish exports by volume. This globalization of fish trade, coupled with technological developments in food production, handling, processing and distribution, and the increasing awareness and demand of consumers for safe and high quality food have put food safety and quality assurance high in public awareness and a priority for many governments. Consequently, many countries have tightened food safety controls, imposing additional costs and requirements on imports. As early as 1980, there was an international drive towards adopting preventative HACCP-based safety and quality systems. More recently, there has been a growing awareness of the importance of an integrated, multidisciplinary approach to food safety and quality throughout the entire food chain. Implementation of this approach requires an enabling policy and regulatory environment at national and international levels with clearly defined rules and standards, establishment of appropriate food control systems and programmes at national and local levels, and provision of appropriate training and capacity building. This paper discusses the international framework for fish safety and quality, with particular emphasis on the United Nation's Food and Agricultural Organization's (FAO) strategy to promote international harmonization and capacity building

Assuring fish safety and quality in international fish trade

Energy Technology Data Exchange (ETDEWEB)

Ababouch, Lahsen [United Nations, Food and Agricultural Organization, Chief, Fish Utilization and Marketing Services, FAO Headquarters, F-607 Rome (Italy)]. E-mail lahsen.ababouch@fao.org

2006-07-01

International trade in fishery commodities reached US$ 58.2 billion in 2002, a 5% improvement relative to 2000 and a 45% increase over 1992 levels. Within this global trade, developing countries registered a net trade surplus of US$ 17.4 billion in 2002 and accounted for almost 50% by value and 55% of fish exports by volume. This globalization of fish trade, coupled with technological developments in food production, handling, processing and distribution, and the increasing awareness and demand of consumers for safe and high quality food have put food safety and quality assurance high in public awareness and a priority for many governments. Consequently, many countries have tightened food safety controls, imposing additional costs and requirements on imports. As early as 1980, there was an international drive towards adopting preventative HACCP-based safety and quality systems. More recently, there has been a growing awareness of the importance of an integrated, multidisciplinary approach to food safety and quality throughout the entire food chain. Implementation of this approach requires an enabling policy and regulatory environment at national and international levels with clearly defined rules and standards, establishment of appropriate food control systems and programmes at national and local levels, and provision of appropriate training and capacity building. This paper discusses the international framework for fish safety and quality, with particular emphasis on the United Nation's Food and Agricultural Organization's (FAO) strategy to promote international harmonization and capacity building.

International views on nuclear safety

International Nuclear Information System (INIS)

Birkhofer, A.

2002-01-01

Safety has always been an important objective in nuclear technology. Starting with a set of sound physical principles and prudent design approaches, safety concepts have gradually been refined and cover now a wide range of provisions related to design, quality and operation. Research, the evaluation of operating experiences and probabilistic risk assessments constitute an essential basis and international co-operation plays a significant role in that context. Concerning future developments a major objective for new reactor concepts, such as the EPR, is to practically exclude a severe core damage accident with large scale consequences outside the plant. (author)

Strengthening the Global Nuclear Safety Regime. INSAG-21. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2014-01-01

The Global Nuclear Safety Regime is the framework for achieving the worldwide implementation of a high level of safety at nuclear installations. Its core is the activities undertaken by each country to ensure the safety and security of the nuclear installations within its jurisdiction. But national efforts are and should be augmented by the activities of a variety of international enterprises that facilitate nuclear safety - intergovernmental organizations, multinational networks among operators, multinational networks among regulators, the international nuclear industry, multinational networks among scientists, international standards setting organizations and other stakeholders such as the public, news media and non-governmental organizations (NGOs) that are engaged in nuclear safety. All of these efforts should be harnessed to enhance the achievement of safety. The existing Global Nuclear Safety Regime is functioning at an effective level today. But its impact on improving safety could be enhanced by pursuing some measured change. This report recommends action in the following areas: - Enhanced use of the review meetings of the Convention on Nuclear Safety as a vehicle for open and critical peer review and a source for learning about the best safety practices of others; - Enhanced utilization of IAEA Safety Standards for the harmonization of national safety regulations, to the extent feasible; - Enhanced exchange of operating experience for improving operating and regulatory practices; and - Multinational cooperation in the safety review of new nuclear power plant designs. These actions, which are described more fully in this report, should serve to enhance the effectiveness of the Global Nuclear Safety Regime

Acknowledgements [3. international conference on small angle neutron scattering dedicated to the 80 anniversary of Yu.M. Ostanevich, Dubna (Russian Federation), 6-9 June 2016

International Nuclear Information System (INIS)

2017-01-01

The Organizers of the III International Conference on Small Angle Neutron Scattering dedicated to the 80-th anniversary of Yu. M. Ostanevich, acknowledge the financial support from the Grants of the Governmental Plenipotentiary Representatives of Romania, Slovakia, Czech Republic, scientific projects of the Cooperation Programmes JINR-Romania. Special gratitude to the JINR and FLNP administration and staff is expressed. The conference is also dedicated to the 60th Anniversary of the Joint Institute for Nuclear Research, Dubna. (paper)

International nuclear safety experts complete IAEA peer review of German regulatory system

International Nuclear Information System (INIS)

2008-01-01

Full text: An international expert team has today completed a two-week IAEA review of Germany's nuclear regulatory system. The team identified good practices within the system and gave advice on some areas for further improvement. The IAEA has conveyed the initial findings to German authorities but the final report will be submitted within two months. At the request of the Government of the Federal Republic of Germany, the International Atomic Energy Agency (IAEA) assembled a team of 14 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This is a peer review based on IAEA Standards. It is not an inspection, nor an audit. The scope of the mission was limited to the safety regulation of nuclear power plants. Experts from Canada, the Czech Republic, Finland, France, Japan, the Netherlands, Republic of Korea, Spain, Switzerland, the UK, the US and from the IAEA took part in the mission, which was conducted from 7 to 19 September in Bonn, Stuttgart and Berlin. The main basis for the review was a well-prepared self-assessment made by the Federal Ministry of Environment, Nature Conservation and Nuclear Safety (BMU) and the Ministry of Environment of the federal state of Baden-Wuerttemberg (UM BW). 'The team members were impressed by the extensive preparation and dedication of the staff both at BMU and UM BW to excellence in nuclear safety,' said Mike Weightman, IRRS Team Leader and Chief Inspector of the UK nuclear regulatory body, the Nuclear Directorate of the Health and Safety Executive. 'We hope the IRRS mission will facilitate further improvements in the safety regulation of nuclear power in Germany and throughout the world.' 'Germany's invitation to undergo such a detailed review is a clear demonstration of its openness and commitment to continuously improve nuclear safety regulation,' said Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division. Among the particular strengths of BMU and UM BW associated with their

International conference on the operational safety performance in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2005-01-01

In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

Inherent and passive safety measures in accelerator driven systems: a safety strategy for ADS

International Nuclear Information System (INIS)

Maschek, W.; Rineiski, A.; Morita, K.; Flad, M.

2001-01-01

The efficiency of Accelerator Driven Systems (ADSs) for the transmutation and incineration of nuclear waste is strongly related to the utilization of so-called dedicated fuels. In the ideal case these fuels should consist of pure TRUs without fertile materials as 238 U or 232 Th to achieve highest incineration/transmutation rates. Dedicated fuels still have to be developed and programs are under way for their fabrication, irradiation and testing. These fertile-free fuels may suffer from deteriorated thermal or thermo-mechanical properties, as a reduced melting point, reduced thermal conductivity or even thermal instability. First analyses have shown that the use of dedicated fuels may lead to a strong deterioration of the safety parameters of the reactor core as e.g. the void worth, the Doppler or the kinetics quantities as neutron generation time and β eff . In addition, a dedicated core may contain multiple ''critical'' fuel masses, resulting in a considerable recriticality potential. Current knowledge on these dedicated fuels suggests that ''critical'' reactors may not be feasible, because of safety reasons. However, for ADSs, the salient hope has been promoted that due to the subcriticality of the system the poor safety features of such fuels could be coped with. Analyses are presented which show potential safety problems for such dedicated cores. Respecting the results of these analyses a safety strategy is proposed along the lines of defense approach in analogy with ideas formerly developed for fast reactors. Inherent and passive safety measures are integrated into the various defense lines. (author)

Development of Safety Review Guide for the Periodic Safety Review of Reactor Vessel Internals

International Nuclear Information System (INIS)

Park, Jeongsoon; Ko, Hanok; Kim, Seonjae; Jhung, Myungjo

2013-01-01

Aging management of the reactor vessel internals (RVIs) is one of the important issues for long-term operation of nuclear power plants (NPPs). Safety review on the assessment and management of the RVI aging is conducted through the process of a periodic safety review (PSR). The regulatory body should check that reactor facilities sustain safety functions in light of degradation due to aging and that the operator of a nuclear power reactor establishes and implements management program to deal with degradation due to aging in order to guarantee the safety functions and the safety margin as a result of PSR. KINS(Korea Institute of Nuclear Safety) has utilized safety review guides (SRG) which provide guidance to KINS staffs in performing safety reviews in order to assure the quality and uniformity of staff safety reviews. The KINS SRGs for the continued operation of pressurized water reactors (PWRs) published in 2006 contain areas of review regarding aging management of RVIs in chapter 2 (III.2.15, Appendix 2.0.1). However unlike the SRGs for the continued operation, KINS has not officially published the SRGs for the PSR of PWRs, but published them as a form of the research report. In addition to that, the report provides almost same review procedures for aging assessment and management of RVIs with the ones provided in the SRGs for the continued operation, it cannot provide review guidance specific to PSRs. Therefore, a PSR safety review guide should be developed for RVIs in PWRs. In this study, a draft PSR safety review guide for reactor vessel internals in PWRs is developed and provided. In this paper, a draft PSR safety review guide for reactor vessel internals (PSR SRG-RVIs) in PWRs is introduced and main contents of the draft are provided. However, since the PSR safety review guides for areas other than RVIs in the pressurized water reactors (PWRs) are expected to be developed in the near future, the draft PSR SRG-RVIs should be revisited to be compatible with

The International Criticality Safety Benchmark Evaluation Project on the Internet

International Nuclear Information System (INIS)

Briggs, J.B.; Brennan, S.A.; Scott, L.

2000-01-01

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) was initiated in October 1992 by the US Department of Energy's (DOE's) defense programs and is documented in the Transactions of numerous American Nuclear Society and International Criticality Safety Conferences. The work of the ICSBEP is documented as an Organization for Economic Cooperation and Development (OECD) handbook, International Handbook of Evaluated Criticality Safety Benchmark Experiments. The ICSBEP Internet site was established in 1996 and its address is http://icsbep.inel.gov/icsbep. A copy of the ICSBEP home page is shown in Fig. 1. The ICSBEP Internet site contains the five primary links. Internal sublinks to other relevant sites are also provided within the ICSBEP Internet site. A brief description of each of the five primary ICSBEP Internet site links is given

Safety sans Frontières: An International Safety Culture Model.

Science.gov (United States)

Reader, Tom W; Noort, Mark C; Shorrock, Steven; Kirwan, Barry

2015-05-01

The management of safety culture in international and culturally diverse organizations is a concern for many high-risk industries. Yet, research has primarily developed models of safety culture within Western countries, and there is a need to extend investigations of safety culture to global environments. We examined (i) whether safety culture can be reliably measured within a single industry operating across different cultural environments, and (ii) if there is an association between safety culture and national culture. The psychometric properties of a safety culture model developed for the air traffic management (ATM) industry were examined in 17 European countries from four culturally distinct regions of Europe (North, East, South, West). Participants were ATM operational staff (n = 5,176) and management staff (n = 1,230). Through employing multigroup confirmatory factor analysis, good psychometric properties of the model were established. This demonstrates, for the first time, that when safety culture models are tailored to a specific industry, they can operate consistently across national boundaries and occupational groups. Additionally, safety culture scores at both regional and national levels were associated with country-level data on Hofstede's five national culture dimensions (collectivism, power distance, uncertainty avoidance, masculinity, and long-term orientation). MANOVAs indicated safety culture to be most positive in Northern Europe, less so in Western and Eastern Europe, and least positive in Southern Europe. This indicates that national cultural traits may influence the development of organizational safety culture, with significant implications for safety culture theory and practice. © 2015 Society for Risk Analysis.

Nuclear safety: an international approach: the convention on nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1994-01-01

This paper is a general presentation of the IAEA Convention on Nuclear Safety which has already be signed by 50 countries and which is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The paper gives a review of its development and some key provisions for a better understanding of how this agreement will operate in practice. The Convention consists of an introductory preamble and four chapters consisting of 35 articles dealing with: the principal objectives, definitions and scope of application; the various obligations (general provisions, legislation, responsibility and regulation, general safety considerations taking into account: the financial and human resources, the human factors, the quality assurance, the assessment and verification of safety, the radiation protection and the emergency preparedness; the safety of installations: sitting, design and construction, operation); the periodic meetings of the contracting parties to review national reports on the measures taken to implement each of the obligations, and the final clauses and other judicial provisions common to international agreements. (J.S.). 1 append

Nuclear safety research collaborations between the US and Russian Federation international nuclear safety centers

International Nuclear Information System (INIS)

Hill, D.J; Braun, J.C; Klickman, A.E.; Bugaenko, S.E; Kabanov, L.P; Kraev, A.G.

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the U.S. Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the U. S. Center at Argonne National Laboratory in October 1995. MINATOM established the Russian Center at the Research and Development Institute of Power Engineering in Moscow in July 1996. In April 1998 the Russian center became an independent, autonomous organization under MINATOM. The goals of the centers are to: cooperate in the development of technologies associated with nuclear safety in nuclear power engineering. be international centers for the collection of information important for safety and technical improvements in nuclear power engineering. maintain a base for fundamental knowledge needed to design nuclear reactors.The strategic approach that is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors

International contributions of JNES on seismic safety areas

International Nuclear Information System (INIS)

Ebisawa, Katsumi; Uchiyama, Yuichi; Yamada, Hiroyuki

2010-01-01

JNES actively promotes the international cooperation in seismic safety areas, aiming to play a role as the important international hub for it. To meet this purpose, JNES is now mainly focusing on the increased support of the international organizations including IAEA and the technological improvement in the seismic related assessment of Asian countries. This paper summarizes these efforts made by JNES. (author)

Quality assurance requirements for dedication process in Angra 1

Energy Technology Data Exchange (ETDEWEB)

Baliza, Ana Rosa, E-mail: baliza@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Angra dos Reis, RJ (Brazil). Departamento GQO.G; Morghi, Youssef, E-mail: ymo@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

In Brazil the regulatory body is CNEN (Comissao Nacional de Energia Nuclear), according to its requirements, when there is not a Brazilian standard, the utilities shall follow the requirements of the designer. For Angra 1, the designer is an American company - Westinghouse. So, the requirements for dedication of U.S. NRC (United States Nuclear Regulatory Commission) shall be applied, these requirements are in 10CFR21 - Reporting of Defects and Noncompliance. According to 10CFR21, when applied to nuclear power plants licensed dedication is an acceptance process undertaken to provide reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program standard for nuclear power plant. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. (author)

Quality assurance requirements for dedication process in Angra 1

International Nuclear Information System (INIS)

Baliza, Ana Rosa

2015-01-01

In Brazil the regulatory body is CNEN (Comissao Nacional de Energia Nuclear), according to its requirements, when there is not a Brazilian standard, the utilities shall follow the requirements of the designer. For Angra 1, the designer is an American company - Westinghouse. So, the requirements for dedication of U.S. NRC (United States Nuclear Regulatory Commission) shall be applied, these requirements are in 10CFR21 - Reporting of Defects and Noncompliance. According to 10CFR21, when applied to nuclear power plants licensed dedication is an acceptance process undertaken to provide reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety function and, in this respect, is deemed equivalent to an item designed and manufactured under a quality assurance program standard for nuclear power plant. This assurance is achieved by identifying the critical characteristics of the item and verifying their acceptability by inspections, tests, or analyses by the purchaser or third-party dedicating entity. (author)

Can international safety overcome national prejudice

International Nuclear Information System (INIS)

Thomas, S.

1986-01-01

Following the accident at the Chernobyl nuclear power plant, a proposal has been made that the International Atomic Energy Agency (IAEA) should carry out a programme of reactor assessments and inspections to ensure that the plant is competently run. The 13 proposals for improving safety that arose from the recent IAEA meeting in Vienna about the events at Chernobyl are listed. They also propose international collaboration on many points. This article draws attention to the difficulties in achieving international cooperation. Comparison is made with the case of international air and marine transport and an attempt to get an agreement to reduce emissions of acid rain precursors by 30%. The essential requirements for international regulation are stated. Four specific activities that could be covered are discussed. These are inspection of operating plant, enforcement of minimum standards for routine emissions, establishment of design standards and establishment of post-accident procedures for international co-operation. (UK)

Current status of international cooperation on nuclear safety research

International Nuclear Information System (INIS)

Katsuragi, Satoru

1984-01-01

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

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

International Nuclear Information System (INIS)

Novosel, N.; Rosandic, L.

2010-01-01

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

International handbook of evaluated criticality safety benchmark experiments

International Nuclear Information System (INIS)

2010-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirement 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 over 55,000 pages and contain 516 evaluations with benchmark specifications for 4,405 critical, near critical, or subcritical configurations, 24 criticality alarm placement / shielding configurations with multiple dose points for each, and 200 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. Experiments that are found unacceptable for use as criticality safety benchmark experiments are discussed in these evaluations; however, benchmark specifications are not derived for such experiments (in some cases models are provided in an appendix). Approximately 770 experimental configurations are categorized as unacceptable for use as criticality safety benchmark experiments. Additional evaluations are in progress and will be

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

International Nuclear Information System (INIS)

1994-12-01

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

Dedicated Filter for Robust Occupancy Grid Mapping

Directory of Open Access Journals (Sweden)

KS Nagla

2015-03-01

Full Text Available Sensor based perception of the environment is an emerging area of the mobile robot research where sensors play a pivotal role. For autonomous mobile robots, the fundamental requirement is the convergent of the range information in to high level internal representation. Internal representation in the form of occupancy grid is commonly used in autonomous mobile robots due to its various advantages. There are several sensors such as vision sensor, laser rage finder, and ultrasonic and infrared sensors etc. play roles in mapping. However the sensor information failure, sensor inaccuracies, noise, and slow response are the major causes of an error in the mapping. To improve the reliability of the mobile robot mapping multisensory data fusion is considered as an optimal solution. This paper presents a novel architecture of sensor fusion frame work in which a dedicated filter (DF is proposed to increase the robustness of the occupancy grid for indoor environment. The technique has been experimentally verified for different indoor test environments. The proposed configuration shows improvement in the occupancy grid with the implementation of dedicated filters.

Canadian Nuclear Safety Commission's intern program

International Nuclear Information System (INIS)

Gilmour, P.E.

2002-01-01

The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

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

International Nuclear Information System (INIS)

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

2013-01-01

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

Progress toward international agreement to improve reactor safety

International Nuclear Information System (INIS)

Lieberman, J.I.; Graham, B.

1993-01-01

Representatives of nearly one-half of the 114 member states of the International Atomic Energy Agency (IAEA), including the United States, have participated in the development of an international nuclear safety conventions proposed multilateral treaty to improve civil nuclear power reactor safety. A preliminary draft of the convention has been developed (referred to as the draft convention for this report), but discussions are continuing, and when the final convention text will be completed and presented to IAEA member states for signature is uncertain. This report responds to the former and current Chairman's request that we provide information on the development of the nuclear safety convention, including a discussion of (1) the draft convention's scope and objectives, (2) how the convention will be implemented and monitored, (3) the views of selected country representatives on what provisions should be included in the draft convention, and (4) the convention's potential benefits and limitations

78 FR 14912 - International Aviation Safety Assessment (IASA) Program Change

Science.gov (United States)

2013-03-08

... Aviation Safety Assessment (IASA) Program Change AGENCY: Federal Aviation Administration (FAA), DOT. ACTION..., into the U.S., or codeshare with a U.S. air carrier, complies with international aviation safety... subject to that country's aviation safety oversight can serve the United States using its own aircraft or...

Japan's international cooperation programs on seismic safety of nuclear power plants

International Nuclear Information System (INIS)

Sanada, Akira

1997-01-01

MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

International nuclear safety center database on material properties

International Nuclear Information System (INIS)

Fink, J.K.

1996-01-01

International nuclear safety center database on the following material properties is described: fuel, cladding,absorbers, moderators, structural materials, coolants, concretes, liquid mixtures, uranium dioxide

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

The main requirements of the International Basic Safety Standards

International Nuclear Information System (INIS)

Webb, G.A.M.

1998-01-01

The main requirements of the new international basic safety standards are discussed, including such topics as health effects of ionizing radiations, the revision of basic safety standards, the requirements for radiation protection practices, the requirements for intervention,and the field of regulatory infrastructures. (A.K.)

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

OpenAIRE

Elizabeth M. Borycki

2015-01-01

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

International standardization of safety requirements for fast reactors

International Nuclear Information System (INIS)

2011-06-01

Japan Atomic Energy Agency (JAEA) is conducting the FaCT (Fast Reactor Cycle Technology Development) project in cooperation with Japan Atomic Power Company (JAPC) and Mitsubishi FBR systems inc. (MFBR), where an advanced loop-type fast reactor named JSFR (Japan Sodium-cooled Fast Reactor) is being developed. It is important to develop software technologies (a safety guideline, safety design criteria, safety design standards etc.) of FBRs as well as hardware ones (a reactor plant itself) in order to address prospective worldwide utilization of FBR technology. Therefore, it is expected to establish a rational safety guideline applicable to the JSFR and harmonized with national nuclear-safety regulations as well, including Japan, the United States and the European Union. This report presents domestic and international status of safety guideline development for sodium-cooled fast reactors (SFRs), results of comparative study for safety requirements provided in existing documents and a proposal for safety requirements of future SFRs with a roadmap for their refinement and worldwide utilization. (author)

National and international safety, safeguardability and security

International Nuclear Information System (INIS)

Wakabayashi, Hiroaki

1987-01-01

All nuclear power and fuel cycle facility development must comply with the predecided national regulation and security codes which each country's Atomic Energy Commission stipulates. Those codes will basically evolve as technologies and the social system will develop, change and shift. It is also to be noted that the IAEA's international guidelines have been adopted particularly by developing countries as a good reference for their proper establishment of their safety codes. The report first discusses the plant safety regulation of the inherently safe reactors in comparison to the existing code (or licensing guide) of the Japanese government. Then the new trend seen now in a regulatory body (the US NRC) is reviewed and a proposal of the smooth transition into the new philosophy is presented. In the second part of the paper, the fuel safeguarding and facility security (or physical protection) are discussed, because in the case of inherently safe reactors like ISER-PIUS, it seems that safety has much more to do with the safeguard and the security. In the third part, the international relevances to the security of the ISER-PIUS are discussed, because any ISER-PIUS will be meaningless unless they are used extensively and freely in any part of the world precluding the security concerns. In collaborative use of the state and international codes, regulatory guides and practices, it is evident that ISER-PIUS system can clear the requirements on all the aspects by ample margin. (Nogami, K.)

EPR meeting international safety standards with margin

International Nuclear Information System (INIS)

Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

2005-01-01

The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

EPR meeting international safety standards with margin

International Nuclear Information System (INIS)

Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

2005-01-01

The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification in with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

KEOPS and other VENUS experiments dedicated to the criticality safety of a MOX fuel fabrication facility

International Nuclear Information System (INIS)

Lance, Benoit; Van Den Hende, Paul; Marloye, Daniel; Basselier, Jacques; Libon, Henri; De Vleeschhauwer, Marc; Moerenhout, Jeremie; Baeten, Peter

2005-01-01

The qualification scheme of criticality computer codes for Pu bearing powders lies upon databases which suffer from a lack of recent experimental results. As a MOX manufacture, BELGONUCLEAIRE is especially concerned by criticality safety and would like to address such an issue by launching with SCK-CEN an International Programme called KEOPS. (author)

International review of Kursk unit 1 in-depth safety analysis report

International Nuclear Information System (INIS)

Chouha, M.; Bolshov, L.; Butcher, P.; Janke, R.; Parsons, T.; Weber, J.P.

2004-01-01

The paper presents the objectives, organisation, main findings and conclusions of the international review of the Kursk unit 1 safety analysis report (K1IRSR). The K1IRSR was administered by RISKAUDIT IRSN/GRS international and carried out by international experts from 7 western countries plus the Russian Federation, under the supervision of the safety review group (SRG) of the European bank for reconstruction and development (EBRD). The project was financed by the nuclear safety account (NSA) administered by the EBRD. The Russian experts worked under a contract with IBRAE financed by Rosenergoatom. The main conclusions were that the SAR followed a correct approach, broadly in line with Russian and international guidance documents, but needed improvement in structure and content. It established that the safety level of the unit has been increased significantly by the modernisation programme. The important deviations of the unit from current Russian regulations and the IAEA safety issues for RBMK are either fully resolved or are being addressed to the extent possible by compensatory measures to further reduce the risk. The K1IRSR experts have made a number of recommendations for improvement of the K1SAR. The authors agreed to take the recommendations into account in future revision of the K1SAR. (orig.)

ICSBEP-2007, International Criticality Safety Benchmark Experiment Handbook

International Nuclear Information System (INIS)

Blair Briggs, J.

2007-01-01

1 - Description: The Critically Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United Sates Department of Energy. The project quickly became an international effort as scientist from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization of Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA). This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material. The example calculations presented do not constitute a validation of the codes or cross section data. The work of the ICSBEP is documented as an International Handbook of Evaluated Criticality Safety Benchmark Experiments. Currently, the handbook spans over 42,000 pages and contains 464 evaluations representing 4,092 critical, near-critical, or subcritical configurations and 21 criticality alarm placement/shielding configurations with multiple dose points for each and 46 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. The handbook is intended for use by criticality safety analysts to perform necessary validations of their calculational techniques and is expected to be a valuable tool for decades to come. The ICSBEP Handbook is available on DVD. You may request a DVD by completing the DVD Request Form on the internet. Access to the Handbook on the Internet requires a password. You may request a password by completing the Password Request Form. The Web address is: http://icsbep.inel.gov/handbook.shtml 2 - Method of solution: Experiments that are found

Proceedings of international conference dedicated to the seventieth anniversary of Physical-technical institute, SPA 'Physics-Sun' 'Fundamental and applied problems of physics'

International Nuclear Information System (INIS)

Lutpullaev, S.L.; Atabaev, I.G.; Abdurakhmanov, A.A.

2013-11-01

The International conference dedicated to the seventieth anniversary of Physical-technical institute, SPA 'Physics-Sun' 'Fundamental and applied problems of physics' was held on 14-15 November, 2013 in Tashkent, Uzbekistan. Specialists discussed various aspects of modern problems of relativistic nuclear physics and physics of atomic nuclei, solid state physics, various applications of new materials. More than 225 talks were presented in the meeting. (k.m.)

NPP safety and personnel training. XII International conference. Abstracts

International Nuclear Information System (INIS)

2011-01-01

The 12th International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7, 2011. The issues of nuclear technologies safety are considered.The problems of life-cycle management of nuclear facilities are discussed. The criteria of assessment of physical protection systems of nuclear facilities are presented [ru

Russian Minatom nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

Royen, J.

1999-01-01

An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

European and International Standards on health and safety in welding

International Nuclear Information System (INIS)

Howe, A

2009-01-01

A number of European and International Standards on health and safety in welding have been published in recent years and work on several more is nearing completion. These standards have been prepared jointly by the International Standards Organization (ISO) and the European Committee for Standardization (CEN). The standards development work has mostly been led by CEN/TC 121/SC 9, with excellent technical input from experts within Europe; but work on the revision of published standards, which has recently gathered pace, is now being carried out by ISO/TC 44/SC 9, with greater international involvement. This paper gives an overview of the various standards that have been published, are being revised or are under development in this field of health and safety in welding, seeking to (i) increase international awareness of published standards, (ii) encourage wider participation in health and safety in welding standards work and (iii) obtain feedback and solicit comments on standards that are currently under development or revision. Such an initiative is particularly timely because work is currently in progress on the revision of one of the more important standards in this field, namely EN ISO 10882:2001 Health and safety in welding and allied processes- Sampling of airborne particles and gases in the operator's breathing zone - Part 1: Sampling of airborne particles.

The role of the International Atomic Energy Agency in radiation and waste safety

International Nuclear Information System (INIS)

Wrixon, A.D.; Ortiz-Lopez, P.

1999-01-01

The International Atomic Energy Agency is specifically required by its Statute 'to establish or adopt ... standards of safety for protection of health and minimization of danger to life and property ... and to provide for the application of these standards ...'. Standards encompass three main elements: legally binding international undertakings among States; globally agreed international safety standards; and the provision for facilitating the application of those standards. Radiation safety standards are national responsibilities, but there is considerable value in formulating harmonized approaches throughout the world. The Agency has attempted to do this by establishing internationally agreed safety standards and by prompting their application. Of prime importance are the Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. These deal with the basic requirements that must be met in order to ensure an adequate standard of safety. More detailed guidance on the application of these requirements is given in Safety Guides established under them. Fuller technical support is given in a series of Safety Reports. A number of Safety Guides are relevant to this meeting. An existing Safety Guide on exemption is being revised to cover related topics such as exclusion and clearance, and this is the subject of a separate presentation. As part of the programme to combat illicit trafficking in radioactive materials, a new Safety Guide on the topic is being developed. Both are near completion. Another Safety Guide is being produced to elaborate the requirements in the Basic Safety Standards on the safety of radioactive sources. The topics of illicit trafficking in radioactive materials and the safety of radioactive sources were given added impetus by resolutions of the last General Conference of the Agency. This paper provides an overview of these activities of the Agency. (author)

International antiterrorist conventions concerning the safety of air transport

Directory of Open Access Journals (Sweden)

Jacek BARCIK

2008-01-01

Full Text Available In this article the international law regulations are presented concerning the civilian safety of the air transport. The history concerning air terrorism and international antiterrorist conventions was described in detail, involving The Chicago Convention, The Tokyo Convention, The Hague Convention and Montreal Convention.

Management of operational safety in nuclear power plants. INSAG-13. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

1999-01-01

The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. Engineering issues have received close attention from the nuclear community over many years. However, it is only in the last decade or so that organizational and cultural issues have been identified as vital to achieving safe operation. INSAG's publication No. 4 has been widely recognized as a milestone in advancing thinking about safety culture in the nuclear community and more widely. The present report deals with the framework for safety management that is necessary in organizations in order to promote safety culture. It deals with the general principles underlying the management of operational safety in a systematic way and provides guidance on good practices. It also draws on the results of audits and reviews to highlight how shortfalls in safety management have led to incidents at nuclear power plants. In addition, several specific issues are raised which are particularly topical in view of organizational changes that are taking place in the nuclear industry in various countries. Advice is given on how safety can be managed during organizational change, how safety

24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 1. Papers 1-27

International Nuclear Information System (INIS)

1999-01-01

The first volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The main topic in the volume is the contribution of nondestructive testing to the reactor safety from an international point of view. All 20 papers are separately analyzed for this database. (orig.)

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

Safety culture in nuclear installations: Summary of an international topical meeting

International Nuclear Information System (INIS)

Carnino, A.; Derrough, M.; Weimann, G.

1996-01-01

An international topical meeting, Safety Culture in Nuclear Installations, was organized by the American Nuclear Society (ANS) Austria Local Section, cosponsored by the ANS Nuclear Reactor Safety and Human Factors Divisions in cooperation with the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA/OECD) and held in Vienna April 24-28, 1995. Some 250 experts from 30 different countries and organizations took part in the 85 paper presentations and two workshops. The concept of safety culture was initially used in the first International Nuclear Safety Advisory Group (INSAG) report on the Chernobyl accident analysis report in 1986. Although some elements of safety culture have been used over the years in nuclear safety activities, the new phrase safety culture and the concept were found interesting as highlighting the 'soft' aspects of safety and as encompassing more than human errors. Unfortunately, for many years it was used more in the way of identifying lack of safety culture. Conscious of this application, INSAG further developed the safety culture concept in the INSAG 4 report: The report contains a definition, the universal aspects of safety culture, the two main components of safety culture management and individual behaviour, and performance indicators of a good safety culture. This report is now quite famous and adopted with some additions or complementary definitions by many institutes and organizations for their daily activities

Japan`s international cooperation programs on seismic safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

1997-03-01

MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

Cost effective nuclear commercial grade dedication

International Nuclear Information System (INIS)

Maletz, J.J.; Marston, M.J.

1991-01-01

This paper describes a new computerized database method to create/edit/view specification technical data sheets (mini-specifications) for procurement of spare parts for nuclear facility maintenance and to develop information that could support possible future facility life extension efforts. This method may reduce cost when compared with current manual methods. The use of standardized technical data sheets (mini-specifications) for items of the same category improves efficiency. This method can be used for a variety of tasks, including: Nuclear safety-related procurement; Non-safety related procurement; Commercial grade item procurement/dedication; Evaluation of replacement items. This program will assist the nuclear facility in upgrading its procurement activities consistent with the recent NUMARC Procurement Initiative. Proper utilization of the program will assist the user in assuring that the procured items are correct for the applications, provide data to assist in detecting fraudulent materials, minimize human error in withdrawing database information, improve data retrievability, improve traceability, and reduce long-term procurement costs

National Transportation Safety Board : weak internal control impaired financial accountability

Science.gov (United States)

2001-09-28

The U. S. General Accounting Office (GAO) was asked to review the National Transportation Safety Board's (NTSB) internal controls over selected types of fiscal year expenditures. They were asked to determine whether internal control weaknesses were a...

Homogenised constitutive model dedicated to reinforced concrete plates subjected to seismic solicitations

International Nuclear Information System (INIS)

Combescure, Christelle

2013-01-01

Safety reassessments are periodically performed on the EDF nuclear power plants and the recent seismic reassessments leaded to the necessity of taking into account the non-linear behaviour of materials when modeling and simulating industrial structures of these power plants under seismic solicitations. A large proportion of these infrastructures is composed of reinforced concrete buildings, including reinforced concrete slabs and walls, and literature seems to be poor on plate modeling dedicated to seismic applications for this material. As for the few existing models dedicated to these specific applications, they present either a lack of dissipation energy in the material behaviour, or no micromechanical approach that justifies the parameters needed to properly describe the model. In order to provide a constitutive model which better represents the reinforced concrete plate behaviour under seismic loadings and whose parameters are easier to identify for the civil engineer, a constitutive model dedicated to reinforced concrete plates under seismic solicitations is proposed: the DHRC (Dissipative Homogenised Reinforced Concrete) model. Justified by a periodic homogenisation approach, this model includes two dissipative phenomena: damage of concrete matrix and internal sliding at the interface between steel rebar and surrounding concrete. An original coupling term between damage and sliding, resulting from the homogenisation process, induces a better representation of energy dissipation during the material degradation. The model parameters are identified from the geometric characteristics of the plate and a restricted number of material characteristics, allowing a very simple use of the model. Numerical validations of the DHRC model are presented, showing good agreement with experimental behaviour. A one dimensional simplification of the DHRC model is proposed, allowing the representation of reinforced concrete bars and simplified models of rods and wire mesh

Experience with nuclear safety standards development in non-governmental international organizations

International Nuclear Information System (INIS)

Becker, K.

1985-01-01

Besides the IAEA as a 'governmental' organization dealing with basic safety recommendations addressed primarily to the national regulatory bodies in developing countries, two closely related non-governmental international standards organizations have gained extensive experience in the field of nuclear standardization. Over more than 25 years since their formation, both (a) the International Organization for Standardization's (ISO) Technical Committee 85 'Nuclear Energy', in particular in its Sub-Committee 3 'Reactor Technology and Safety' and (b) the International Electrotechnical Commission's (IEC) Technical Committee 45 'Nuclear Instrumentation' have published numerous standards. A brief review is given of these, draft standards, and other documents planned to become international standards. Many of them deal with rather specialized topics typical for 'industrial' standards such as standardized procedures, instruments, methods, materials, test methods, terminology, and signs and symbols, but others are directly related to more basic safety issues. In some areas such as quality assurance, seismic aspects of siting and terminology, there has been in the past occasional overlap in the activities of the NUSS programme, IEC and ISO. Letters of Understanding have since 1981 contributed to clarifying the borderlines and to avoiding redundant efforts. Also, some experiences and problems are described arising, for example, from the harmonization of different national safety philosophies and traditions into universally accepted international standards, and the transfer of international standards into national standards systems. Finally, based on a recent comprehensive compilation of some 3300 nuclear standards and standards projects, an attempt is made to present a cost/benefit analysis and an outlook on future developments. (author)

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)

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

International Nuclear Information System (INIS)

Novosel, N.

2011-01-01

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

International review on safety requirements for the prototype fast breeder reactor “Monju”

International Nuclear Information System (INIS)

2016-01-01

In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report “Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju” taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)

Dedication of Stotz-Kontakt switches for Spanish utility owners

International Nuclear Information System (INIS)

Lopez Vergara, T.; Martin de la Torre, M.; Alminana, J.

1996-01-01

The Spanish Utility Owners Group commissioned Empresarios Agrupados to perform the work for the dedication of the S280 series of Stotz-KONTAKT switches and two of its possible accessories. As a results of this process, the components can be used in safety-related applications in the conditions and locations expected. This article describes the different phases of the dedication process: Technical Evaluation considering the application of switches as new or alternative elements, Acceptance Process and Purchasing Documentation. It sets out the main conclusion drawn from each phase. It also includes details of the activities performed by Empresarios Agrupados as part of the seismic qualification of components: selection of the sample to be tested, the definition of electrical tests before and after the seismic test, and the mounting, electrical powering, operating requirements and monitoring of components during seismic tests. (Author)

Implementation of probabilistic safety concepts in international codes

International Nuclear Information System (INIS)

Borges, J.F.

1977-01-01

Recent progress in the implementation of safety concepts in international structure codes is briefly presented. Special attention is paid to the work of the Joint-Committee on Structural Safety. The discussion is centered on some problems such as: safety differentiation, definition and combination of actions, spaces for checking safety and non-linear structural behaviour. When discussing safety differentiation it should be considered that the total probability of failure derives from a theoretical probability of failure and a probability of failure due to error and gross negligence. Optimization of design criteria should take into account both causes of failure. The quantification of reliability implies a probabilistic idealization of all basic variables. Steps taken to obtain an improved definition of different types of actions and rules for their combination are described. Safety checking can be carried out in terms of basic variables, action-effects, or any other suitable variable. However, the advantages and disadvantages of the different types of formulation should be discussed, particularly in the case of non-linear structural behaviour. (orig.) [de

Safety in an international work environment: CERN

CERN Document Server

Potter, K.

1990-01-01

The European Laboratory for Particle Physics (CERN) has recently completed a new accelerator. The installation of this accelerator and its experimental areas represents an example of harmonization of safety rules in supranational areas, as CERN is an international organization and the machine is housed in a tunnel of 26.7 km circumference, of which 20 km is on French territory and 6.7 km on Swiss territory. The work was carried out by a large number of firms from all over Europe, CERN staff and physicists and technicians from all over the world, and represented almost 4 million working hours. The safety organization chosen and applied with the agreement of the two host-State safety authorities is described and the resulting application, including the results in terms of accident statistics, from the installation of the machine, experimental areas and detectors are presented.

Existing and future international standards for the safety of radioactive waste disposal

International Nuclear Information System (INIS)

Linsley, G.

1999-01-01

In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

A fresh start of nuclear safety regulation and international perspective

International Nuclear Information System (INIS)

Oshima, Kenzo

2013-01-01

It should be explained more to the outside modestly the Fukushima nuclear accident would be a man-made complex disaster, which might be reluctant to do but not be neglected. Utmost efforts to change inward-looking attitude and reform safety culture should be done so as to prevent superficial reflection of the Fukushima nuclear accident. Since all nuclear regulatory functions ('3S': safety, security, safeguards) were integrated in Nuclear Regulation Authority (NRA), NRA and secretariat of NRA became more responsible for international response, and strengthening of organization system and human resources development would be an urgent necessity. This article described present stage of NRA focusing on international dimension including personal views. Overseas strong concern over the Fukushima nuclear accident and international communications were reviewed. The Fukushima nuclear accident started from natural disaster and enlarged as a man-made complex disaster with many human factors (mainly inaction, wilful negligence) overlapping and safety culture flawed. Examples of overseas and Japanese action plan to learn and absorb lessons from the Fukushima accident were introduced. NRA's started activities on inviting IAEA's IRRS and OPPAS as soon as ready, strengthening nuclear security measures, safeguards to prevent nuclear proliferation, bilateral cooperation and international advisors were also presented. (T. Tanaka)

Dedicating time to volunteering : Values, engagement, and commitment to beneficiaries

NARCIS (Netherlands)

Shantz, A.; Saksida, T.; Alfes, K.

2014-01-01

A moderated mediation model was developed to explain the variation in the amount of time volunteers dedicate to their chosen voluntary cause. Data from 534 volunteers of an international aid and development agency in the United Kingdom revealed a positive relationship between prosocial values and

International cooperation in production inspections

International Nuclear Information System (INIS)

Limousin, S.

2009-01-01

Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

International Conference of Ukrainian Nuclear Society ''NPP's safety and protection''(annotations)

International Nuclear Information System (INIS)

Barbashev, S.V.

1997-01-01

The abstracts of reports submitted to the Conference include: - New developments of the safe nuclear installations; - NPP ecological safety; - Methods of personnel and population protection; - Waste management safety (at transportation, processing and storage); - Spent nuclear fuel management; - NPP life extension and decommissioning; - Public opinion as an element of NPP safety; - Training of personnel, scientific support and safety culture; - Forecasting of nuclear power and industry safe development; - Development of international cooperation in nuclear power

Engine with pulse-suppressed dedicated exhaust gas recirculation

Science.gov (United States)

Keating, Edward J.; Baker, Rodney E.

2016-06-07

An engine assembly includes an intake assembly, a spark-ignited internal combustion engine, and an exhaust assembly. The intake assembly includes a charge air cooler disposed between an exhaust gas recirculation (EGR) mixer and a backpressure valve. The charge air cooler has both an inlet and an outlet, and the back pressure valve is configured to maintain a minimum pressure difference between the inlet of the charge air cooler and an outlet of the backpressure valve. A dedicated exhaust gas recirculation system is provided in fluid communication with at least one cylinder and with the EGR mixer. The dedicated exhaust gas recirculation system is configured to route all of the exhaust gas from the at least one cylinder to the EGR mixer for recirculation back to the engine.

The Nuclear Energy Agency: Strengthening Nuclear Safety Technology and Regulation Through Effective International Cooperation

International Nuclear Information System (INIS)

Nieh, H.

2016-01-01

The NEA provides an effective forum for international co-operation on nuclear safety and regulatory issues in its specific task groups, working parties and expert groups, as well as through joint international safety research projects. In these activities, NEA member countries work together to share and analyse data and experiences, gain consensus and develop approaches that can be applied within each country’s governmental processes. Through effective international co-operation, NEA member countries have worked together to develop actions for improving their regulatory frameworks and nuclear installation safety. As a result of these efforts, safety improvements and further harmonisation have been realized in the areas operating reactors, new reactors, human and organisational factors and nuclear safety research. At the NEA, technical and programmatic work under the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI), joint safety research projects and the Multinational Design Evaluation Programme (MDEP) have helped NEA member countries to ensure a high standard for nuclear safety and to further develop the technical knowledge base. (author)

CERN safety expert receives international award

CERN Multimedia

2005-01-01

On 18 December 2004, the President of the Swiss Electro-technical Committee, Martin Reichle (left), presented the award to Helmut Schönbacher. Helmut Schönbacher, of the Safety Commission at CERN, has received, the "1906 Award" of the International Electrotechnical Commission (IEC) for his standardisation work on the influence of ionizing radiation on insulating materials. From 1986 until 2004, Schönbacher was leader of a working group on radiation composed of internationally recognised experts. It edited standards of the IEC 60544 series on the determination of the effects of ionizing radiation on electrical insulating materials. The working group also edited three IEC Technical Reports on the determination of long-term radiation ageing in polymers. This standardisation work and long-term experience from CERN on the radiation ageing of materials also contributed to research coordination programmes of the International Atomic Energy Agency (IAEA). From 1968 until 1988, Schönbacher was a member of the Rad...

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

International Nuclear Information System (INIS)

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

2009-01-01

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

Developing international safety standards for the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Metcalf, P.

2001-01-01

In the context of the International Atomic Energy Agency's (IAEA) programme to create a corpus of internationally accepted Radioactive Waste Safety Standards (RADWASS), focus is currently being placed on establishing standards for the 'geological disposal of radioactive waste'. This is a challenging task and to help the standards development process there is a need to stimulate discussion of some of the associated scientific and technical issues. A number of position papers developed in recent years by a subgroup of the Waste Safety Standards Committee (WASSC), the subgroup on Principles and Criteria for Radioactive Waste Disposal, address many of the relevant issues. These include a common safety based framework for radioactive waste disposal, appropriate time frames for safety assessment, different possible indicators of long-term safety, the safety implications of reversibility and retrievability, the assessment of possible human intrusion into the repository, the role and limitations of institutional control, establishing reference critical groups and biospheres for long-term assessment, and what is meant by 'compliance' with the standards. These papers will be discussed at a Specialists Meeting to be held at the IAEA in June 2001 as a means of establishing the extent to which they enjoy the general support of experts. In order to broaden that consensus, the conclusions reached at the Specialists Meeting on the issues listed above will be presented and discussed with participants at a number of international meetings. Later this year, a draft safety standard on the geological disposal of radioactive waste which takes account of the consensus positions reached through the various consultations will be submitted for the consideration of Waste Safety Standards Committee (WASSC), the officially approved body within the IAEA for the review and approval of waste safety standards. The Committee is made up of government appointed radioactive waste regulators

International conference on safety culture in nuclear installations. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The industry literature provides a great deal of insight at the artefact and espoused value levels, although as yet it remains somewhat disorganized. There is, however, an overall lack of understanding of the assumption level of safety culture. The IAEA has organised the conference on safety culture for better understanding of the safety culture issues on the international level.

International conference on safety culture in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2002-01-01

Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The industry literature provides a great deal of insight at the artefact and espoused value levels, although as yet it remains somewhat disorganized. There is, however, an overall lack of understanding of the assumption level of safety culture. The IAEA has organised the conference on safety culture for better understanding of the safety culture issues on the international level

Internal Arc: People safety in the electrical wiring

International Nuclear Information System (INIS)

Inchausti, J. M.

2009-01-01

The aim of this article is to describe the internal arc phenomenon, an extremely fast, almost explosive and unattended process of transformation form an initial electric power to the generation of a pressure and heat wave inside the medium its produced its consequences for safety, current methods of limiting them and current regulations in general for equipment used in medium-voltage electrical distribution networks. Taking into account that this type of equipment is found thought the distribution network in both public buildings and unrestricted access areas, safety (of operators and the general public) must be taken into account in the design of equipment and installations to minimize the risk of internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which the manufacturer has to takes steps to minimize the risks of an internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which an internal arc occurring, it is understood to be vitally important that users, installers and designers of Medium Voltage installations are familiar with the installation conditions stated by the manufacturer and thus avoid risks. (Author) 14 refs

Management of Operational Safety in Nuclear Power Plants. INSAG-13. A report by the International Nuclear Safety Advisory Group (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. Engineering issues have received close attention from the nuclear community over many years. However, it is only in the last decade or so that organizational and cultural issues have been identified as vital to achieving safe operation. INSAG's publication No. 4 has been widely recognized as a milestone in advancing thinking about safety culture in the nuclear community and more widely. The present report deals with the framework for safety management that is necessary in organizations in order to promote safety culture. It deals with the general principles underlying the management of operational safety in a systematic way and provides guidance on good practices. It also draws on the results of audits and reviews to highlight how shortfalls in safety management have led to incidents at nuclear power plants. In addition, several specific issues are raised which are particularly topical in view of organizational changes that are taking place in the nuclear industry in various countries. Advice is given on how safety can be managed during organizational change, how

The role of international atomic energy agency in maintaining nuclear safety competence

International Nuclear Information System (INIS)

Aro, I.; Mazour, T.

2000-01-01

This paper provides information how International Atomic Energy Agency can assist Member States in maintaining and developing nuclear safety competence. The topics covered include the development of safety standards, organisation of nuclear safety related conferences, provision of safety reviews, organisation of training courses and topical workshops and publication of training related documents. Usefulness of these activities for competence development is discussed. (author)

International safety standards and regulatory practices and their application to Brazilian nuclear power plants - a realistic view

International Nuclear Information System (INIS)

Almeida, Claudio; Camargo, Claudio

1999-01-01

An international nuclear safety regime is being established through a series of binding safety conventions, voluntarily adopted international safety standards and an accompanying peer review process. The basis for the evaluation of each country performance within this international regime should be the international practices. However, local conditions should be taken into account to avoid undue stress of the limited resources available to countries with a limited nuclear power programme. This work reviews the current international nuclear safety and discusses the application of some international practices to the Brazilian situation, considering the peculiarities of the national nuclear power programme and the limitations of the available financial and human resources. (author)

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

Science.gov (United States)

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

2015-04-01

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

Conclusions and Recommendations of the IAEA International Conference on Topical Issues in Nuclear Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Main Conclusions and Recommendations of International Conference on Topical Issues in Nuclear Installation Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Application of patient safety indicators internationally: a pilot study among seven countries.

Science.gov (United States)

Drösler, Saskia E; Klazinga, Niek S; Romano, Patrick S; Tancredi, Daniel J; Gogorcena Aoiz, Maria A; Hewitt, Moira C; Scobie, Sarah; Soop, Michael; Wen, Eugene; Quan, Hude; Ghali, William A; Mattke, Soeren; Kelley, Edward

2009-08-01

To explore the potential for international comparison of patient safety as part of the Health Care Quality Indicators project of the Organization for Economic Co-operation and Development (OECD) by evaluating patient safety indicators originally published by the US Agency for Healthcare Research and Quality (AHRQ). A retrospective cross-sectional study. Acute care hospitals in the USA, UK, Sweden, Spain, Germany, Canada and Australia in 2004 and 2005/2006. Routine hospitalization-related administrative data from seven countries were analyzed. Using algorithms adapted to the diagnosis and procedure coding systems in place in each country, authorities in each of the participating countries reported summaries of the distribution of hospital-level and overall (national) rates for each AHRQ Patient Safety Indicator to the OECD project secretariat. Each country's vector of national indicator rates and the vector of American patient safety indicators rates published by AHRQ (and re-estimated as part of this study) were highly correlated (0.821-0.966). However, there was substantial systematic variation in rates across countries. This pilot study reveals that AHRQ Patient Safety Indicators can be applied to international hospital data. However, the analyses suggest that certain indicators (e.g. 'birth trauma', 'complications of anesthesia') may be too unreliable for international comparisons. Data quality varies across countries; undercoding may be a systematic problem in some countries. Efforts at international harmonization of hospital discharge data sets as well as improved accuracy of documentation should facilitate future comparative analyses of routine databases.

Requirements and international co-operation in nuclear safety for evolutionary light water reactors

International Nuclear Information System (INIS)

Carnino, A.

1999-01-01

The principles of safety are now well known and implemented world-wide, leading to a situation of harmonisation in accordance with the Convention on Nuclear Safety. Future reactors are expected not only to meet current requirements but to go beyond the safety level presently accepted. To this end, technical safety requirements, as defined by the IAEA document Safety Fundamentals, need be duly considered in the design, the risks to workers and population must be decreased, a stable, transparent and objective regulatory process, including an international harmonisation with respect to licensing of new reactors, must be developed, and the issue of public acceptance must be addressed. Well-performing existing installations are seen as a prerequisite for an improved public acceptability; there should be no major accidents, the results from safety performance indicators must be unquestionable, and compliance with internationally harmonised criteria is essential. Economical competitiveness is another factor that influences the acceptability; the costs for constructing the plant, for its operation and maintenance, for the fuel cycle, and for the final decommissioning are of paramount importance. Plant simplification, longer fuel cycles, life extension are appealing options, but safety will have first priority. The IAEA can play an important role in this field, by providing peer reviews by teams of international experts and assistance to Member States on the use of its safety standards. (author)

Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

International Nuclear Information System (INIS)

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

2000-01-01

The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kisner, Roger A [ORNL; Mullens, James Allen [ORNL; Wilson, Thomas L [ORNL; Wood, Richard Thomas [ORNL; Korsah, Kofi [ORNL; Qualls, A L [ORNL; Muhlheim, Michael David [ORNL; Holcomb, David Eugene [ORNL; Loebl, Andy [ORNL

2007-08-01

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

International Nuclear Information System (INIS)

Kisner, Roger A.; Mullens, James Allen; Wilson, Thomas L.; Wood, Richard Thomas; Korsah, Kofi; Qualls, A.L.; Muhlheim, Michael David; Holcomb, David Eugene; Loebl, Andy

2007-01-01

Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented

International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

International Nuclear Information System (INIS)

2011-01-01

Full text: Senior nuclear regulators today concluded a Workshop on the Lessons Learned from the IAEA Integrated Regulatory Review Service (IRRS) Missions. The U.S. Nuclear Regulatory Commission (NRC) hosted the workshop, in cooperation with the International Atomic Energy Agency, in Washington, DC, from 26 to 28 October 2011. About 60 senior regulators from 22 IAEA Member States took part in this workshop. The IRRS programme is an international peer review service offered by the IAEA to its Member States to provide an objective evaluation of their nuclear safety regulatory framework. The review is based on the internationally recognized IAEA Safety Standards. ''The United States Nuclear Regulatory Commission was pleased to host the IAEA's IRRS meeting this week. The discussions over the past three days have provided an important opportunity for regulators from many countries to come together to strengthen the international peer review process,'' said U.S. NRC Chairman Gregory B. Jaczko. ''Especially after the Fukushima Daiichi accident, the global community recognizes that IRRS missions fill a vital role in strengthening nuclear safety and security programs around the world, and we are proud to be a part of this important effort.'' The IAEA Action Plan on Nuclear Safety includes actions focused towards strengthening the existing IAEA peer reviews, incorporating lessons learned and improving their effectiveness. The workshop provided a platform for the exchange of information, experience and lessons learned from the IRRS missions, as well as expectations for the IRRS programme for the near future. Further improvements in the planning and implementation of the IRRS missions in the longer term were discussed. A strong commitment of all relevant national authorities to the IRRS programme was identified as a key element of an effective regulatory framework. The conclusions of the workshop will be issued in November 2011 and the main results will be reported to the IAEA

Procurement Engineering Process for Commercial Grade Item Dedication

International Nuclear Information System (INIS)

Park, Jong-Hyuck; Park, Jong-Eun; Kwak, Tack-Hun; Yoo, Keun-Bae; Lee, Sang-Guk; Hong, Sung-Yull

2006-01-01

Procurement Engineering Process for commercial grade item dedication plays an increasingly important role in operation management of Korea Nuclear Power Plants. The purpose of the Procurement Engineering Process is the provision and assurance of a high quality and quantity of spare, replacement, retrofit and new parts and equipment while maximizing plant availability, minimizing downtime due to parts unavailability and providing reasonable overall program and inventory cost. In this paper, we will review the overview requirements, responsibilities and the process for demonstrating with reasonable assurance that a procured item for potential nuclear safety related services or other essential plant service is adequate with reasonable assurance for its application. This paper does not cover the details of technical evaluation, selecting critical characteristics, selecting acceptance methods, performing failure modes and effects analysis, performing source surveillance, performing quality surveys, performing special tests and inspections, and the other aspects of effective Procurement Engineering and Commercial Grade Item Dedication. The main contribution of this paper is to provide the provision of an overview of Procurement Engineering Process for commercial grade item

Proceedings of the international symposium on research reactor safety operations and modifications

International Nuclear Information System (INIS)

1990-03-01

The International Symposium on Research Reactor Safety, Operations and Modifications was organized by the International Atomic Energy Agency in cooperation with Atomic Energy of Canada Limited-Research Company. The main objectives of this Symposium were: (1) to exchange information and to discuss current perspectives and concerns relating to all aspects to research reactor safety, operations, and modifications; and, (2) to present views and to discuss future initiatives and directions for research reactor design, operations, utilization, and safety. The symposium topics included: research reactor programmes and experience; research reactor design safety and analysis; research reactor modifications and decommissioning; research reactor licensing; and new research reactors. These topics were covered during eight oral sessions and three poster sessions. These Proceedings include the full text of the 93 papers presented. The subject of Symposium was quite wide-ranging in that it covered essentially all aspects of research reactor safety, operations, and modifications. This was considered to be appropriate and timely given the 326 research reactors currently in operation in some 56 countries; given the degree of their utilization which ranges from pure and applied research to radioisotopes production to basic training and manpower development; and given that many of these reactors are undergoing extensive modifications, core conversions, power upratings, and are becoming the subject of safety reassessment and regulatory reviews. Although the Symposium covered many topics, the majority of papers and discussions tended to focus mainly on research reactor safety. This was seen as a clear sign of the continuing recognition of the fundamental importance of identifying and addressing, particularly through international cooperation, issues and concerns associated with research reactor safety

The IAEA International Seismic Safety Centre and IAEA safety standards for site evaluation and design of NPPs

International Nuclear Information System (INIS)

Godoy, A.; Sollogoub, P; )

2009-01-01

This presentation covers the following topics: 'Lessons learned' from the occurrence of strong natural events, (tsunamis, earthquakes, hurricanes, etc.) The International Seismic Safety Centre as a global focal point for the nuclear engineering community in those fields. A need for international cooperation, openness and transparency – Sharing of experience

Musculoskeletal MRI: dedicated systems

International Nuclear Information System (INIS)

Masciocchi, C.; Barile, A.; Satragno, L.

2000-01-01

The ''dedicated'' MRI units have characteristics of high diagnostic accuracy and lower installation and management costs as compared with whole-body systems. The dedicated MRI units are easy to install. The low weight allows their installation also under unfavorable circumstances. In a dedicated system cost-effectiveness and ease of installation must be accompanied by the capability of providing high-quality images. In our experience, the high number of examinations performed, the most part of which provided with the surgical controls, allowed an accurate evaluation of the diagnostic potentialities of the dedicated magnet. We were not able to perform the examinations in only 3 % of cases due to the physical shape of the patient and the clinical condition of the patient which may hinder the correct positioning of the limb. The overlapping of the diagnostic accuracy of the E-scan and Artoscan units in the study of the lower limbs, compared with whole-body units and surgery, prompted us to exploit the potentialities of the E-Scan in the study of the shoulder. We had a good correlation between E-Scan, whole-body units, and surgical findings, which confirmed the high diagnostic accuracy of the dedicated system. In conclusion, in our experience carried out in the musculoskeletal system, the dedicated magnets showed promising results. Their diagnostic reliability and utility was comparable to that obtained from conventional units operating at higher magnetic fields. (orig.)

Enlightenment on international cooperation for nuclear safety in China in light of Fukushima nuclear accident

International Nuclear Information System (INIS)

Fu Jie; Feng Yi; Luan Haiyan; Meng Yue; Zhang Ou

2013-01-01

This thesis elaborates on the impact of Fukushima nuclear accident on global nuclear power development and subsequent international activities carried out by major countries. It analyses significance of international cooperation in ensuring nuclear safety and promoting nuclear power development and makes some suggestions to further strengthen the international cooperation on nuclear safety in China. (authors)

New Possibilities for development of the internal health and safety organisation

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, Per Langå

2004-01-01

Research from several countries indicates that the internal health and safety organisation in most companies is placed in an appendix position. A possibility for developing a stronger and more effective health and safety organisation is to introduce learning. This approach has been applied...... in a Danish network project with eleven companies. The results indicate that health and safety managers and safety representatives have difficulties in fulfilling the role as change agents in mastering such a development project. Only three of the eleven companies turned out to be able to implement successful...

Dedication

OpenAIRE

2013-01-01

This work is dedicated, to my mom, Bridget, and my dad, (the late) Daniel Enwerem, who taught me to respect people but not fear them; and to those who are engaged or have been victims in the struggle for an egalitarian society in Nigeria.

Research on international cooperation for nuclear and radiation safety

International Nuclear Information System (INIS)

Cheng Jianxiu

2013-01-01

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

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

The nuclear power safety programme of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Rosen, M.

1981-01-01

The expanded role of the IAEA in the field of nuclear power safety will be discussed. Emphasis will be given to the NUSS program (the letters being an acronym for Nuclear Safety Standards) to establish internationally accepted safety codes and guides for nuclear power plants dealing with governmental regulatory organizations, siting, design, operation and quality assurance. Other activities discussed will be advisory services, exchange of information and training, emergency accident assistance, and technical assistance. (orig./RW)

Russian MINATOM nuclear safety research strategic plan. An international review

International Nuclear Information System (INIS)

1999-03-01

The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

International Conference on Human and Organizational Aspects of Assuring Nuclear Safety. Exploring 30 years of Safety Culture. Programme and Abstracts

International Nuclear Information System (INIS)

2016-01-01

Thirty years ago, the International Nuclear Safety Advisory Group concluded, in its investigation of the Chernobyl accident, that one of the key lessons to be learned from that accident was the importance of a strong safety culture to maintain safe operations. Almost five years have now passed since the accident at the Fukushima Daiichi nuclear power plant, and the need to implement a systemic approach to safety that takes into account the complex and dynamic sociotechnical systems comprising nuclear infrastructure is one of the main lessons emerging from investigations. This conference will allow an international audience to take a step back and reflect upon the knowledge accumulated in the areas of human and organizational factors (HOF), safety culture and leadership for safety over the past 30 years. The objectives of the conference are to: • Review the experience gained with regard to HOF, safety culture and leadership for safety; • Share and gather experiences related to current developments, approaches, methods and research in the areas of HOF, safety culture and leadership for safety; and • Identify the future needs for building organizational resilience capabilities in order to further strengthen defence in depth for nuclear facilities and activities. The special focus of the conference will be on safety culture and the past 30 years of developments in this area.

International review on safety requirements for the prototype fast breeder reactor “Monju” (Translated document)

International Nuclear Information System (INIS)

2016-02-01

In response to the lessons learned from the serious nuclear accidents at the TEPCO's Fukushima Daiichi Nuclear Power Stations, an advisory committee, which was set up by the Japan Atomic Energy Agency, issued the report “Safety Requirements Expected to the Prototype Fast Breeder Reactor Monju” taking into account the SFR specific safety characteristics in July 2014. The report was reviewed by the leading international experts on SFR safety from five countries and one international organization in order to obtain independent and objective evaluation. The international review comments on each subsection were collected and compiled, and then a summary of results was derived through the discussion at the review meeting and individual feedbacks. As a result the basic concept for prevention of severe accidents and mitigation of their consequences of Monju is appropriate in consideration of SFR specific safety characteristics, and is in accordance with international common understanding. (author)

The WIPP transportation system: Dedicated to safety

International Nuclear Information System (INIS)

Ward, T.; McFadden, M.

1993-01-01

When developing a transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites, the Department of Energy (DOE) recognized and addressed many challenges. Shipments of waste to the Waste Isolation Pilot Plant (WIPP) were to cover a twenty-five year period and utilize routes covering over twelve thousand miles in twenty-three states. Enhancing public safety by maximizing the payload, thus reducing the number of shipments, was the primary objective. To preclude the requirement for overweight permits, the DOE started with a total shipment weight limit of 80,000 pounds and developed an integrated transportation system consisting of a Type ''B'' package to transport the material, a lightweight tractor and trailer, stringent driver requirements, and a shipment tracking system referred to as ''TRANSCOM''

Safety of radiation sources and security of radioactive materials. Proceedings of an international conference

International Nuclear Information System (INIS)

1999-01-01

This International Conference, hosted by the Government of France and co-sponsored by the European Commission, the International Criminal Police Organization (Interpol) and the World Customs Organization (WCO), was the first one devoted to the safety of radiation sources and the security of radioactive materials and - for the first time - brought together radiation safety experts, regulators, and customs and police officers, who need to closely co-operate for solving the problem of illicit trafficking. The technical sessions reviewed the state of the art of twelve major topics, divided into two groups: the safety of radiation sources and the security of radioactive materials. The safety part comprised regulatory control, safety assessment techniques, engineering and managerial measures, lessons from experience, international cooperation through reporting systems and databases, verification of safety through inspection and the use of performance indicators for a regulatory programme. The security part comprised measures to prevent breaches in the security of radioactive materials, detection and identification techniques for illicit trafficking, response to detected cases and seized radioactive materials, strengthening awareness, training and exchange of information. The Conference was a success in fostering information exchange through the reviews of the state of the art and the frank and open discussions. It raised awareness of the need for Member States to ensure effective systems of control and for preventing, detecting and responding to illicit trafficking in radioactive materials. The Conference finished by recommending investigating whether international undertakings concerned with an effective operation of national systems for ensuring the safety of radiation sources and security of radioactive materials

Application of patient safety indicators internationally: a pilot study among seven countries

NARCIS (Netherlands)

Drösler, Saskia E.; Klazinga, Niek S.; Romano, Patrick S.; Tancredi, Daniel J.; Gogorcena Aoiz, Maria A.; Hewitt, Moira C.; Scobie, Sarah; Soop, Michael; Wen, Eugene; Quan, Hude; Ghali, William A.; Mattke, Soeren; Kelley, Edward

2009-01-01

To explore the potential for international comparison of patient safety as part of the Health Care Quality Indicators project of the Organization for Economic Co-operation and Development (OECD) by evaluating patient safety indicators originally published by the US Agency for Healthcare Research and

Fast reactor safety: proceedings of the international topical meeting. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

Fast reactor safety: proceedings of the international topical meeting. Volume 1

International Nuclear Information System (INIS)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences

Study Regarding the Provision of Security and Safety in the International Maritime Transport

Directory of Open Access Journals (Sweden)

Liliana POPA

2011-11-01

Full Text Available The security in transport has become a crucial issue internationally, especially after the terrorist attacks of September 2001 and even more recently. Maritime, along with aviation, is considered a sensitive and of high-risk transport sector, in terms of security. Moreover, topics related to safety in maritime transport have become very important over the past decades mostly because of the numerous maritime accidents putting in danger both human lives and the environment. Taking into account the global dimension of maritime transport along with the fact that the participation of Asia in the world trade during the past decade has been substantial, the current maritime safety and security practices apply for all areas. This can only be achieved through the application of high standards and regulations setting the prerequisites for safe and secure navigation. In this direction, a significant number of Directives, Regulations and Initiatives on maritime safety and security have been introduced by international and European organizations, such as the International Maritime Organization, (I.M.O., the International Labour Organization (I.L.O. and the European Union (EU. In the framework of this analysis, the levels of compliance of European and Asian countries, regarding the international legislation, is examined while special emphasis is given on the problems and difficulties encountered during the implementation processes. Furthermore, a number of recommendations aiming to enhance the existing levels of safety and security in maritime transport in both examined area is provided.

Economic approaches to measuring the significance of food safety in international trade.

Science.gov (United States)

Caswell, J A

2000-12-20

International trade in food products has expanded rapidly in recent years. This paper presents economic approaches for analyzing the effects on trade in food products of the food safety requirements of governments and private buyers. Important economic incentives for companies to provide improved food safety arise from (1) public incentives such as ex ante requirements for sale of a product with sufficient quality and ex post penalties (liability) for sale of products with deficient quality, and (2) private incentives for producing quality such as internal performance goals (self-regulation) and the external (certification) requirements of buyers. The World Trade Organization's Sanitary Phytosanitary Agreement facilitates scrutiny of the benefits and costs of country-level regulatory programs and encourages regulatory rapprochement on food safety issues. Economists can help guide risk management decisions by providing estimates of the benefits and costs of programs to improve food safety and by analyzing their effect on trade in food products.

Evaluating the Effectiveness of an Educational Intervention to Improve the Patient Safety Attitudes of Intern Pharmacists.

Science.gov (United States)

Walpola, Ramesh L; Fois, Romano A; McLachlan, Andrew J; Chen, Timothy F

2017-02-25

Objective. To evaluate the effectiveness of a face-to-face educational intervention in improving the patient safety attitudes of intern pharmacists. Methods. A patient safety education program was delivered to intern pharmacists undertaking The University of Sydney Intern Training Program in 2014. Their patient safety attitudes were evaluated immediately prior to, immediately after, and three-months post-intervention. Underlying attitudinal factors were identified using exploratory factor analysis. Changes in factor scores were examined using analysis of variance. Results. Of the 120 interns enrolled, 95 (78.7%) completed all three surveys. Four underlying attitudinal factors were identified: attitudes towards addressing errors, questioning behaviors, blaming individuals, and reporting errors. Improvements in all attitudinal factors were evident immediately after the intervention. However, only improvements in attitudes towards blaming individuals involved in errors were sustained at three months post-intervention. Conclusion. The educational intervention was associated with short-term improvements in pharmacist interns' patient safety attitudes. However, other factors likely influenced their attitudes in the longer term.

The international regime for nuclear safety after Fukushima; Das internationale System nuklearer Sicherheit nach Fukushima

Energy Technology Data Exchange (ETDEWEB)

Raetzke, Christian [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

2014-05-15

The Chernobyl catastrophe in 1986 lead to a new foundation of the international regime for nuclear safety: the 1994 Convention on Nuclear Safety introduced for the first time obligations on adhering states to adopt certain principles to achieve a high level of safety. The Convention, however, does not contain detailed standards, nor does it install a 'hard' mechanism for control and enforcement. While the system has undoubtedly lead to improvements in nuclear safety worldwide, it was not able to detect and remedy the deficiencies in the Japanese system. Ideas voiced immediately after the Fukushima accident to take a further decisive step towards a more stringent international system seemed not to be met with enthusiasm. The general tendency is to use the existing instruments and mechanisms in a more effective manner. However, very recently (in April 2014) the member states of the Convention on Nuclear Safety decided to stage a diplomatic conference with the aim to amend the Convention and to insert safety objectives. Time will eventually show whether this is a first, but decisive step towards the idea of an international system of mandatory and enforceable nuclear safety standards. (orig.)

Methodology for creating dedicated machine and algorithm on sunflower counting

Science.gov (United States)

Muracciole, Vincent; Plainchault, Patrick; Mannino, Maria-Rosaria; Bertrand, Dominique; Vigouroux, Bertrand

2007-09-01

In order to sell grain lots in European countries, seed industries need a government certification. This certification requests purity testing, seed counting in order to quantify specified seed species and other impurities in lots, and germination testing. These analyses are carried out within the framework of international trade according to the methods of the International Seed Testing Association. Presently these different analyses are still achieved manually by skilled operators. Previous works have already shown that seeds can be characterized by around 110 visual features (morphology, colour, texture), and thus have presented several identification algorithms. Until now, most of the works in this domain are computer based. The approach presented in this article is based on the design of dedicated electronic vision machine aimed to identify and sort seeds. This machine is composed of a FPGA (Field Programmable Gate Array), a DSP (Digital Signal Processor) and a PC bearing the GUI (Human Machine Interface) of the system. Its operation relies on the stroboscopic image acquisition of a seed falling in front of a camera. A first machine was designed according to this approach, in order to simulate all the vision chain (image acquisition, feature extraction, identification) under the Matlab environment. In order to perform this task into dedicated hardware, all these algorithms were developed without the use of the Matlab toolbox. The objective of this article is to present a design methodology for a special purpose identification algorithm based on distance between groups into dedicated hardware machine for seed counting.

Safety of a dedicated brain MRI protocol in patients with a vagus nerve stimulator.

Science.gov (United States)

de Jonge, Jeroen C; Melis, Gerrit I; Gebbink, Tineke A; de Kort, Gérard A P; Leijten, Frans S S

2014-11-01

Although implanted metallic devices constitute a relative contraindication to magnetic resonance imaging (MRI) scanning, the safety of brain imaging in a patient with a vagus nerve stimulator (VNS) is classified as "conditional," provided that specific manufacturer guidelines are followed when a transmit and receive head coil is used at 1.5 or 3.0 Tesla. The aim of this study was to evaluate the safety of performing brain MRI scans in patients with the VNS. From September 2009 until November 2011, 101 scans were requested in 73 patients with the VNS in The Netherlands. Patients were scanned according to the manufacturer's guidelines. No patient reported any side effect, discomfort, or pain during or after the MRI scan. In one patient, a lead break was detected based on device diagnostics after the MRI-scan. However, because no system diagnostics had been performed prior to MR scanning in this patient, it is unclear whether MR scanning was responsible for the lead break. The indication for most scans was epilepsy related. Twenty-six scans (26%) were part of a (new) presurgical evaluation and could probably better have been performed prior to VNS implantation. Performing brain MRI scans in patients with an implanted VNS is safe when a modified MRI protocol is followed. Wiley Periodicals, Inc. © 2014 International League Against Epilepsy.

Towards a binding international governance of nuclear safety: an impossible quest?

International Nuclear Information System (INIS)

Finon, Dominique

2014-01-01

The Fukushima accident again raises the question of the social and economic viability of nuclear technology. On an international basis, it should be necessary to reach the maximum level of safety for every nuclear power plant (NPP) to avoid any further accident in order to preserve the acceptability of the technology. To obtain a significant orientation in upgrading safety standards in matter of NPP design and operation and institutional practices for control and safety in all countries with nuclear facilities, the ideal would be to succeed in setting up a binding international governance. This article examines the incentives and the conditions to achieve it. These incentives on the States appear not to be strong enough at the global level in order that they delegate part of their sovereignty in this domain. It seems that we must be content with a weak governance. This governance combining the role of the IAEA as a facilitator, and different peer pressures mechanisms at the level of the NPP operators, the reactors vendors and the safety authority. We observe that each of these mechanisms is presently being reinforced. But how strong this weak governance is strong enough? (author)

GROWTH OF THE INTERNATIONAL CRITICALITY SAFETY AND REACTOR PHYSICS EXPERIMENT EVALUATION PROJECTS

Energy Technology Data Exchange (ETDEWEB)

J. Blair Briggs; John D. Bess; Jim Gulliford

2011-09-01

Since the International Conference on Nuclear Criticality Safety (ICNC) 2007, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) have continued to expand their efforts and broaden their scope. Eighteen countries participated on the ICSBEP in 2007. Now, there are 20, with recent contributions from Sweden and Argentina. The IRPhEP has also expanded from eight contributing countries in 2007 to 16 in 2011. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments1' have increased from 442 evaluations (38000 pages), containing benchmark specifications for 3955 critical or subcritical configurations to 516 evaluations (nearly 55000 pages), containing benchmark specifications for 4405 critical or subcritical configurations in the 2010 Edition of the ICSBEP Handbook. The contents of the Handbook have also increased from 21 to 24 criticality-alarm-placement/shielding configurations with multiple dose points for each, and from 20 to 200 configurations categorized as fundamental physics measurements relevant to criticality safety applications. Approximately 25 new evaluations and 150 additional configurations are expected to be added to the 2011 edition of the Handbook. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments2' have increased from 16 different experimental series that were performed at 12 different reactor facilities to 53 experimental series that were performed at 30 different reactor facilities in the 2011 edition of the Handbook. Considerable effort has also been made to improve the functionality of the searchable database, DICE (Database for the International Criticality Benchmark Evaluation Project) and verify the accuracy of the data contained therein. DICE will be discussed in separate papers at ICNC 2011. The status of the

76 FR 52016 - NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting

Science.gov (United States)

2011-08-19

... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (11-074)] NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel; Meeting AGENCY: National Aeronautics and Space... meeting of the NASA International Space Station Advisory Committee and the Aerospace Safety Advisory Panel...

NPP safety and personnel training. XII International conference. Abstracts. Volume 2

International Nuclear Information System (INIS)

2011-01-01

The XII International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7 2011. The problems of personnel training for nuclear industry are discussed. The innovation nuclear systems and fuel cycle are considered. The much attention has been given to NPP radiation safety and radioecology issues. The recent high-speed computation and simulation methods used in reactor technology are presented [ru

Nuclear and radiological safety 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-06-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety issued during the period 1980-1994. The following aspects are covered: Uranium mining and milling, Fuel fabrication and storage, Nuclear power plants, Research reactors, Radiation sources and accelerators, Transport of radioactive materials, Waste repositories, Radiation protection, Accident response, Radioactive waste management, Safety analysis, Quality management, Legal and governmental aspects

International laser safety standardization. From the European perspective with an emphasis on materials processing

Energy Technology Data Exchange (ETDEWEB)

Schulmeister, K [Div. of Life Sciences, Dept. of Radiation Protection, Oesterreichisches Forschungszentrum Seibersdorf, 2444 Seibersdorf (Austria)

1997-08-01

This report reviews international standards relevant to the safety of laser products and laser installations, with an emphasis on the safety of laser materials processing from the European perspective. In the first paragraphs an overview of the international standards organisations, their relative roles and ways of developing new standards is given. In the second part of the report, work currently underway in the respective standards committees is summarised and specific standards dealing with different aspects of laser safety are discussed. An appendix contains a list of standards organised in standards organisations (IEC, ISO and EN). (author)

International laser safety standardization. From the European perspective with an emphasis on materials processing

International Nuclear Information System (INIS)

Schulmeister, K.

1997-08-01

This report reviews international standards relevant to the safety of laser products and laser installations, with an emphasis on the safety of laser materials processing from the European perspective. In the first paragraphs an overview of the international standards organisations, their relative roles and ways of developing new standards is given. In the second part of the report, work currently underway in the respective standards committees is summarised and specific standards dealing with different aspects of laser safety are discussed. An appendix contains a list of standards organised in standards organisations IEC, ISO and EN). (author)

Seismic safety programme at NPP Paks. Propositions for coordinated international activity in seismic safety of the WWER-440 V-213

International Nuclear Information System (INIS)

Katona, T.

1995-01-01

This paper presents the Paks NPP seismic safety program, highlighting the specifics of the WWER-440/213 type in operation, and the results of work obtained so far. It covers the following scope: establishment of the seismic safety program (original seismic design, current requirements, principles and structure of the seismic safety program); implementation of the seismic safety program (assessing the seismic hazard of the site, development of the new concept of seismic safety for the NPP, assessing the seismic resistance of the building and the technology); realization of the seismic safety of higher level (technical solutions, drawings, realization); ideas and propositions for coordinated international activity

Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium

International Nuclear Information System (INIS)

1998-04-01

The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper

Upgrading of fire safety in nuclear power plants. Proceedings of an International Symposium

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-01

The document includes 40 papers presented at the International Symposium on Upgrading of Fire Safety in Nuclear Power Plants held in Vienna between 18-21 November 1997. The symposium presentations were grouped in 6 sessions: Fire safety reviews (5 papers), Fire safety analysis - Methodology (6 papers), Fire safety analysis - Applications (3 papers), Panel 1 - Identification of deficiencies in fire safety in nuclear power plants - Operational experience and data (7 papers), Panel 2 - Experience based data in fire safety assessment - Fire safety regulations and licensing (7 papers), Upgrading programmes (10 papers), and a closing session (2 papers). A separate abstract was prepared for each paper Refs, figs, tabs

International co-operation in the field of operational safety

International Nuclear Information System (INIS)

Dupuis, M.C.

1988-10-01

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

Sweden's Co-operation with Eastern Europe in Radiation Safety 2011

International Nuclear Information System (INIS)

Dassen, Lars van; Andersson, Sarmite; Bejarano, Gabriela; Chirman, Inessa; Delalic, Zlatan; Ekblad, Christer; Karlberg, Olof; Klasen, Haakan; Olsson, Kjell; Sandberg, Viviana; Stenberg, Tor; Turner, Roland; Wickman, Barbro

2012-03-01

In 2011, the Swedish Radiation Safety Authority implemented co-operation projects in Russia, Ukraine, Georgia, Lithuania and Moldova, based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Co-operation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security, waste management, nonproliferation as well as radiation protection and emergency preparedness) for the benefit of the host countries and the international community as well as Sweden. This report gives an overview of all the projects implemented in 2011. The project managers from SSM are the cornerstones of our successful work, but all the efforts and dedication by staff members of the facilities and authorities in the mentioned countries are indispensable for the long-term positive outcomes. This report is meant to serve as a detailed account regarding SSM's efforts as part of the Swedish international activities, on which Sweden will report to the Nuclear Security Summit in Seoul. The parties to the G-8 Global Partnership have in June 2011 extended the Global Partnership for ten more years, till 2022. Other international frameworks, such as the UNSC Resolution 1540, remain a vibrant instrument by which UN Member States can exchange information on security concerns and request assistance from each other. The projects that SSM implements in Moldova and Georgia have a reference to the aims and purposes of the UNSC Resolution 1540. Much work has been done in the fields of nuclear security and safety, but there are still lots of issues that need to be taken care of. As such, SSM will continue to do its part for nuclear safety and security at the international level, along the lines and priorities set by our Government

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

Science.gov (United States)

2011-07-07

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

The international standard for protection from ionizing radiation and safety of radiation sources

Energy Technology Data Exchange (ETDEWEB)

Schlesinger, T [Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center

1995-06-01

This document is a review in hebrew of the new 1994 international standard of the IAEA. The new standard title is `Basic safety standards for radiation protection and for the safety of radiation sources`, which were published in the ICRP Pub. 9.

International Nuclear Safety Experts Conclude IAEA Peer Review of Swiss Regulatory Framework

International Nuclear Information System (INIS)

2011-01-01

Full text: A team of international nuclear safety experts today completed a two-week International Atomic Energy Agency (IAEA) review of the regulatory framework for nuclear safety in Switzerland. The Integrated Regulatory Review Service (IRRS) mission noted good practices in the Swiss system and also made recommendations for the nation's nuclear regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI). ''Our team developed a good impression of the independent Swiss regulator - ENSI - and the team considered that ENSI deserves particular credit for its actions to improve Swiss safety capability following this year's nuclear accident in Japan,'' said IRRS Team Leader Jean-Christophe Niel of France. The mission's scope covered the Swiss nuclear regulatory framework for all types of nuclear-related activities regulated by ENSI. The mission was conducted from 20 November to 2 December, mainly at ENSI headquarters in Brugg. The team held extensive discussions with ENSI staff and visited many Swiss nuclear facilities. IRRS missions are peer reviews, not inspections or audits, and are conducted at the request of host nations. For the Swiss review, the IAEA assembled a team of 19 international experts from 14 countries. The experts came from Belgium, Brazil, the Czech Republic, Finland, France, Germany, Italy, the Republic of Korea, Norway, Russia, Slovakia, Sweden, the United Kingdom, and the United States. ''The findings of the IRRS mission will help us to further improve our work. That is part of our safety culture,'' said ENSI Director General Hans Wanner. ''As Switzerland argued at international nuclear safety meetings this year for a strengthening of the international monitoring of nuclear power, we will take action to fulfil the recommendations.'' The IRRS team highlighted several good practices of the Swiss regulatory system, including the following: ENSI requires Swiss nuclear operators to back-fit their facilities by continuously upgrading

Source-book of International Activities Related to the Development of Safety Cases for Deep Geological Repositories

International Nuclear Information System (INIS)

2017-01-01

All national radioactive waste management authorities recognise today that a robust safety case is essential in developing disposal facilities for radioactive waste. To improve the robustness of the safety case for the development of a deep geological repository, a wide variety of activities have been carried out by national programs and international organisations over the past years. The Nuclear Energy Agency, since first introducing the modern concept of the 'safety case', has continued to monitor major developments in safety case activities at the international level. This Source-book summarises the activities being undertaken by the Nuclear Energy Agency, the European Commission and the International Atomic Energy Agency concerning the safety case for the operational and post-closure phases of geological repositories for radioactive waste that ranges from low-level to high-level waste and for spent fuel. In doing so, it highlights important differences in focus among the three organisations

Dedicated accelerator and microprobe line

International Nuclear Information System (INIS)

Malmqvist, K.G.; Hylten, G.; Hult, M.; Haakansson, K.; Knox, J.M.; Larsson, N.P.O.; Nilsson, C.; Pallon, J.; Schofield, R.; Swietlicki, E.; Tapper, U.A.S.; Yang Changyi

1993-01-01

The development of a dedicated facility for nuclear microprobe analysis and the experiences from using it are discussed. The general properties of the present Lund nuclear microprobe will be described and the advantages of using a dedicated accelerator discussed. (orig.)

Academic Outcome Measures of a Dedicated Education Unit Over Time: Help or Hinder?

Science.gov (United States)

Smyer, Tish; Gatlin, Tricia; Tan, Rhigel; Tejada, Marianne; Feng, Du

2015-01-01

Critical thinking, nursing process, quality and safety measures, and standardized RN exit examination scores were compared between students (n = 144) placed in a dedicated education unit (DEU) and those in a traditional clinical model. Standardized test scores showed that differences between the clinical groups were not statistically significant. This study shows that the DEU model is 1 approach to clinical education that can enhance students' academic outcomes.

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

DEFF Research Database (Denmark)

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

2013-01-01

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

Fast reactor safety: proceedings of the international topical meeting. Volume 2

International Nuclear Information System (INIS)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments

Computerized engineering logic for procurement and dedication processes

International Nuclear Information System (INIS)

Tulay, M.P.

1996-01-01

This paper summarizes the work performed for designing the system and especially for calculating on-line expected performance and gives some significant results. In an attempt to better meet the needs of operations and maintenance organizations, many nuclear utility procurement engineering groups have simplified their procedures, developed on-line tools for performing the specification of replacement items, and developed relational databases containing part-level information necessary to automate the procurement process. Although these improvements have helped to reduce the engineering necessary to properly specify and accept/dedicate items for nuclear safety-related applications, a number of utilities have recognized that additional long-term savings can be realized by integrating a computerized logic to assist technical procurement engineering personnel

International Nuclear Safety Center database on thermophysical properties of reactor materials

International Nuclear Information System (INIS)

Fink, J.K.; Sofu, T.; Ley, H.

1997-01-01

The International Nuclear Safety Center (INSC) database has been established at Argonne National Laboratory to provide easily accessible data and information necessary to perform nuclear safety analyses and to promote international collaboration through the exchange of nuclear safety information. The INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor material properties for normal operating conditions, transients, and severe accidents. The initial focus of the database is on thermodynamic and transport properties of materials for water reactors. Materials that are being included in the database are fuel, absorbers, cladding, structural materials, coolant, and liquid mixtures of combinations of UO 2 , ZrO 2 , Zr, stainless steel, absorber materials, and concrete. For each property, the database includes: (1) a summary of recommended equations with uncertainties; (2) a detailed data assessment giving the basis for the recommendations, comparisons with experimental data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equations; and (4) property values tabulated as a function of temperature

Safety assessment guidance in the International Atomic Energy Agency RADWASS Program

Energy Technology Data Exchange (ETDEWEB)

Vovk, I.F.; Seitz, R.R.

1995-12-31

The IAEA RADWASS programme is aimed at establishing a coherent and comprehensive set of principles and standards for the safe management of waste and formulating the guidelines necessary for their application. A large portion of this programme has been devoted to safety assessments for various waste management activities. Five Safety Guides are planned to be developed to provide general guidance to enable operators and regulators to develop necessary framework for safety assessment process in accordance with international recommendations. They cover predisposal, near surface disposal, geological disposal, uranium/thorium mining and milling waste, and decommissioning and environmental restoration. The Guide on safety assessment for near surface disposal is at the most advanced stage of preparation. This draft Safety Guide contains guidance on description of the disposal system, development of a conceptual model, identification and description of relevant scenarios and pathways, consequence analysis, presentation of results and confidence building. The set of RADWASS publications is currently undergoing in-depth review to ensure a harmonized approach throughout the Safety Series.

Changing the internal health and safety organization through organizational learning and change management

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, P.L.

2006-01-01

Research from several countries indicates that the internal health and safety organization is marginalized in most companies, and it is difficult for the professionals to secure a proper role in health and safety on the companies' present agenda. The goal of a Danish project involving a network...... of I I companies was to search for a solution to this problem. The health and safety managers and safety representatives played the role of "change agents" for local projects aiming to develop the health and safety organization. The study showed that 3 of the 11 companies proved to be able to implement...

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

IAEA'S International Working Group on Integrated Transport and Storage Safety case for Dual Purpose Casks

International Nuclear Information System (INIS)

Kumano, Yumiko; Varley, Kasturi; ); Droste, Bernhard; Wolff, Dietmar; Hirose, Makoto; Harvey, John; Reiche, Ingo; McConnell, Paul

2014-01-01

Spent nuclear fuel is generated from the operation of nuclear reactors and it is imperative that it is safely managed following its removal from reactor cores. Reactor pools are usually designed based on the assumption that the fuel will be removed after a short period of time either for reprocessing, disposal, or further storage. As a result of storing higher burn-up fuel, significantly increased time-frame till disposal solutions are prepared, and delays in decisions on strategies for spent fuel management, the volume of spent fuel discharged from reactors which needs to be managed and stored is on the increase. Consequently, additional storage capacity is needed following the initial storage in reactor pools. Options for additional storage include wet storage or dry storage in a dedicated facility or in storage casks. One of these options is the use of a Dual Purpose Cask (DPC), which is a specially designed cask for both storage and transport. The management of spent fuel using a DPC generally involves on-site and off-site transportation before and after storage. Most countries require package design approval for the DPC to be transported. In addition, it is required in many countries to have a licence for storage of the spent fuel in the DPC or a licence for a storage facility that contains DPCs. Therefore, demonstration of compliance of the DPC with national and international transport regulations as well as with the storage requirements is necessary. In order to address this increasing need among Member States, the IAEA established an international working group in 2010 to develop a guidance for integrating safety cases for both storage and transport in a holistic manner. The working group consists of experts from regulatory bodies, Technical Support Organizations, operators for both transportation and storage, and research institutes. This activity is planned to be completed by 2013. Currently, a technical report has been drafted and is expected to be

Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

International Nuclear Information System (INIS)

2010-01-01

This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

Minor actinide burning in dedicated lead-bismuth cooled fast reactors

International Nuclear Information System (INIS)

Hejzlar, P.; Driscoll, M.J.; Kazimi, M.S.; Todreas, N.E.

2001-01-01

The destruction of minor actinides (MA) in dedicated burners is of contemporary interest in Europe and Japan because it requires the deployment of smaller number of special transmutation facilities. A major fraction of Pu from spent LWR fuel can be then burned in PWRs (or fast reactors) using dedicated fertile-free fuel assemblies. However, the design of MA burning fast spectrum cores poses significant challenges because of deterioration of key safety parameters, in particular of the coolant void coefficient. This study proposes the concept of an lead-bismuth eutectic (LBE)-cooled dedicated MA burner having metallic fuel (MA-Pu-Zr) and streaming assemblies to attain acceptable coolant void worth performance. It is shown that a large 1800 MWth fertile-free core containing 37 wt% TRU with very high fraction of MA(59 wt%) from LWR spent fuel can be burned in a first cycle for 700 EFPDs with a very small reactivity swing: less than β eff . Moreover, the reactivity void worth is negative for a fully voided core when all surrounding coolant is kept at reference density. However, the core reactivity increases as coolant density falls from the reference value of 10.25 to 6 g/cm 3 . Because its coolant density coefficient value is less than that of a sodium cooled IFR, the concept provides good potential for the achievement of self-regulation characteristics in unprotected events, provided that small negative fuel temperature feedback can be maintained. (authors)

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Child Passenger Safety Training for Pediatric Interns: Does it Work?

Science.gov (United States)

Morrissey, Dina; Riese, Alison; Violano, Pina; Lapidus, Garry; Baird, Janette; Mello, Michael J

2016-03-01

Evaluate the efficacy of a child passenger safety (CPS) educational intervention on the CPS-related knowledge, attitude and anticipatory guidance behaviors of pediatric interns. All subjects were surveyed at baseline and 6 months. Intervention interns attended a CPS training module which included viewing an educational video, observing a car seat inspection appointment, hands-on practice and completion of a post-intervention survey. All 16 intervention interns completed the initial survey, the intervention and the immediate-post questionnaire. Thirteen (81%) completed the 6-month follow-up. The baseline survey was completed by 27/40 (67%) of control interns, 28/40 (70%) submitted a follow-up. The proportion of intervention interns who self-reported giving CPS guidance at all well-child visits increased by 31.3% (95% CI 6.1,56.5%); the control group had no change. Similar results were seen with self-reported knowledge and attitude. A CPS training module increases pediatric interns' knowledge, improves attitudes, and self-reported behaviors regarding CPS-related anticipatory guidance.

PREFACE: International Scientific and Research Conference on Topical Issues in Aeronautics and Astronautics (dedicated to the 55th anniversary from the foundation of SibSAU)

Science.gov (United States)

2015-10-01

The International Scientific and Research Conference ''Topical Issues in Aeronautics and Astronautics'' is one of the most significant scientific conferences arranged by the Reshetnev Siberian State Aerospace University (SibSAU) which is located in the Krasnoyarsk Region of Russian Federation. In April 2015 this Conference was dedicated to the 55th anniversary from the foundation of the University. Traditionally, the Conference is seen as emblematic of the University's specialty and is annually organized in April, when the first human travelled into space. This Conference is arranged for undergraduate, graduate and postgraduate students, scientists and lecturers, as well as developers, designers and constructors representing leading companies and enterprises of the aerospace sector to give opportunities to present their projects, research work and results. The Conference is a great chance to connect scientists and highly-qualified and skilled specialists with a new community of future scientists and practitioners in the aerospace sector. The Conference proceedings include papers presented by creative young specialists closely connected with aviation and space vehicles - design, production, problem-solving in space machine building and aerospace education, macro- and microeconomic development of the field, new approaches to solving philosophical and social problems, - experienced scientists and specialists, and all those who want to dedicate themselves to aeronautics and astronautics. The selected papers are presented in these proceedings to share University research results, innovations and cutting-edge technologies with the international community to develop aeronautics and astronautics on a global scale.

Dedicated bifurcation stents

Directory of Open Access Journals (Sweden)

Ajith Ananthakrishna Pillai

2012-03-01

Full Text Available Bifurcation percutaneous coronary intervention (PCI is still a difficult call for the interventionist despite advancements in the instrumentation, technical skill and the imaging modalities. With major cardiac events relate to the side-branch (SB compromise, the concept and practice of dedicated bifurcation stents seems exciting. Several designs of such dedicated stents are currently undergoing trials. This novel concept and pristine technology offers new hope notwithstanding the fact that we need to go a long way in widespread acceptance and practice of these gadgets. Some of these designs even though looks enterprising, the mere complex delivering technique and the demanding knowledge of the exact coronary anatomy makes their routine use challenging.

24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 1. Papers 1-27; 24. MPA-Seminar: Sicherheit und Verfuegbarkeit in der Anlagentechnik mit dem Schwerpunkt Integritaet und Lebensdauermanagement. Bd. 1. Vortraege 1-27

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-08-01

The first volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The main topic in the volume is the contribution of nondestructive testing to the reactor safety from an international point of view. All 20 papers are separately analyzed for this database. (orig.)

Evolution of International Space Station Program Safety Review Processes and Tools

Science.gov (United States)

Ratterman, Christian D.; Green, Collin; Guibert, Matt R.; McCracken, Kristle I.; Sang, Anthony C.; Sharpe, Matthew D.; Tollinger, Irene V.

2013-01-01

The International Space Station Program at NASA is constantly seeking to improve the processes and systems that support safe space operations. To that end, the ISS Program decided to upgrade their Safety and Hazard data systems with 3 goals: make safety and hazard data more accessible; better support the interconnection of different types of safety data; and increase the efficiency (and compliance) of safety-related processes. These goals are accomplished by moving data into a web-based structured data system that includes strong process support and supports integration with other information systems. Along with the data systems, ISS is evolving its submission requirements and safety process requirements to support the improved model. In contrast to existing operations (where paper processes and electronic file repositories are used for safety data management) the web-based solution provides the program with dramatically faster access to records, the ability to search for and reference specific data within records, reduced workload for hazard updates and approval, and process support including digital signatures and controlled record workflow. In addition, integration with other key data systems provides assistance with assessments of flight readiness, more efficient review and approval of operational controls and better tracking of international safety certifications. This approach will also provide new opportunities to streamline the sharing of data with ISS international partners while maintaining compliance with applicable laws and respecting restrictions on proprietary data. One goal of this paper is to outline the approach taken by the ISS Progrm to determine requirements for the new system and to devise a practical and efficient implementation strategy. From conception through implementation, ISS and NASA partners utilized a user-centered software development approach focused on user research and iterative design methods. The user-centered approach used on

The safety of nuclear installations as a source of international conflict

International Nuclear Information System (INIS)

Schnurer, H.; Breest, H.C.

1975-01-01

The author outlines safety problems regarding nuclear reactors, nuclear power plants and the whole nuclear fuel cycle and gives an account of national supervision in the FRG. Suggestions are made for easing international conflicts. (HP/LN) [de

47 CFR 69.125 - Dedicated signalling transport.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 3 2010-10-01 2010-10-01 false Dedicated signalling transport. 69.125 Section... (CONTINUED) ACCESS CHARGES Computation of Charges § 69.125 Dedicated signalling transport. (a) Dedicated signalling transport shall consist of two elements, a signalling link charge and a signalling transfer point...

Progress on dedicated animal PET

International Nuclear Information System (INIS)

Liu Wei

2002-01-01

Positron emission tomography, as the leading technology providing molecular imaging of biological processes, is widely used on living laboratory animals. High-resolution dedicated animal PET scanners have been developed. Although the dedicated animal PET faces obstacles and challenges, this advanced technology would play an important role in molecular biomedicine researches, such as diseases study, medicine development, and gene therapy

Advances in the operational safety of nuclear power plants. Proceedings of an international symposium

International Nuclear Information System (INIS)

1996-01-01

The main purpose of the Conference was to provide a forum for exchange of information among around 200 attending experts from 46 Member States and five international organizations, who altogether presented around 80 papers and posters. The Conference presentations were divided into four main topics: Managing and Regulating Safe Operation; Safety Performance and Lessons Learned; Improving Operational Safety Using PSA; Enhancing Safety. Refs, figs, tabs

Sweden's Co-operation with Eastern Europe in Radiation Safety 2011

Energy Technology Data Exchange (ETDEWEB)

Dassen, Lars van; Andersson, Sarmite; Bejarano, Gabriela; Chirman, Inessa; Delalic, Zlatan; Ekblad, Christer; Karlberg, Olof; Klasen, Haakan; Olsson, Kjell; Sandberg, Viviana; Stenberg, Tor; Turner, Roland; Wickman, Barbro

2012-11-01

In 2011, the Swedish Radiation Safety Authority implemented co-operation projects in Russia, Ukraine, Georgia, Lithuania and Moldova, based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Co-operation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security, waste management, nonproliferation as well as radiation protection and emergency preparedness) for the benefit of the host countries and the international community as well as Sweden. This report gives an overview of all the projects implemented in 2011. The project managers from SSM are the cornerstones of our successful work, but all the efforts and dedication by staff members of the facilities and authorities in the mentioned countries are indispensable for the long-term positive outcomes. This report is meant to serve as a detailed account regarding SSM's efforts as part of the Swedish international activities, on which Sweden will report to the Nuclear Security Summit in Seoul. The parties to the G-8 Global Partnership have in June 2011 extended the Global Partnership for ten more years, till 2022. Other international frameworks, such as the UNSC Resolution 1540, remain a vibrant instrument by which UN Member States can exchange information on security concerns and request assistance from each other. The projects that SSM implements in Moldova and Georgia have a reference to the aims and purposes of the UNSC Resolution 1540. Much work has been done in the fields of nuclear security and safety, but there are still lots of issues that need to be taken care of. As such, SSM will continue to do its part for nuclear safety and security at the international level, along the lines and priorities set by our Government.

The International Safety Framework for nuclear power source applications in outer space-Useful and substantial guidance

Science.gov (United States)

Summerer, L.; Wilcox, R. E.; Bechtel, R.; Harbison, S.

2015-06-01

In 2009, the International Safety Framework for Nuclear Power Source Applications in Outer Space was adopted, following a multi-year process that involved all major space faring nations under the auspices of a partnership between the UN Committee on the Peaceful Uses of Outer Space and the International Atomic Energy Agency. The Safety Framework reflects an international consensus on best practices to achieve safety. Following the 1992 UN Principles Relevant to the Use of Nuclear Power Sources in Outer Space, it is the second attempt by the international community to draft guidance promoting the safety of applications of nuclear power sources in space missions. NPS applications in space have unique safety considerations compared with terrestrial applications. Mission launch and outer space operational requirements impose size, mass and other space environment limitations not present for many terrestrial nuclear facilities. Potential accident conditions could expose nuclear power sources to extreme physical conditions. The Safety Framework is structured to provide guidance for both the programmatic and technical aspects of safety. In addition to sections containing specific guidance for governments and for management, it contains technical guidance pertinent to the design, development and all mission phases of space NPS applications. All sections of the Safety Framework contain elements directly relevant to engineers and space mission designers for missions involving space nuclear power sources. The challenge for organisations and engineers involved in the design and development processes of space nuclear power sources and applications is to implement the guidance provided in the Safety Framework by integrating it into the existing standard space mission infrastructure of design, development and operational requirements, practices and processes. This adds complexity to the standard space mission and launch approval processes. The Safety Framework is deliberately

International Handbook of Evaluated Criticality Safety Benchmark Experiments - ICSBEP (DVD), Version 2013

International Nuclear Information System (INIS)

2013-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) became an official activity of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) in 1995. This handbook contains criticality safety benchmark specifications that have been derived from experiments performed at various nuclear critical experiment facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material and to determine criticality alarm requirement 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 nearly 66,000 pages and contain 558 evaluations with benchmark specifications for 4,798 critical, near critical or subcritical configurations, 24 criticality alarm placement/shielding configurations with multiple dose points for each and 200 configurations that have been categorised as fundamental physics measurements that are relevant to criticality safety applications. New to the Handbook are benchmark specifications for Critical, Bare, HEU(93.2)- Metal Sphere experiments referred to as ORSphere that were performed by a team of experimenters at Oak Ridge National Laboratory in the early 1970's. A photograph of this assembly is shown on the front cover

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

International Nuclear Information System (INIS)

2003-10-01

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

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

International Nuclear Information System (INIS)

2003-10-01

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

International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

International Nuclear Information System (INIS)

Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

2008-01-01

Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

Energy Technology Data Exchange (ETDEWEB)

J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

2008-09-01

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR’06 are highlighted, and the future of the two projects is discussed.

INTEGRAL BENCHMARKS AVAILABLE THROUGH THE INTERNATIONAL REACTOR PHYSICS EXPERIMENT EVALUATION PROJECT AND THE INTERNATIONAL CRITICALITY SAFETY BENCHMARK EVALUATION PROJECT

International Nuclear Information System (INIS)

J. Blair Briggs; Lori Scott; Enrico Sartori; Yolanda Rugama

2008-01-01

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) continue to expand their efforts and broaden their scope to identify, evaluate, and provide integral benchmark data for method and data validation. Benchmark model specifications provided by these two projects are used heavily by the international reactor physics, nuclear data, and criticality safety communities. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. The status of the IRPhEP and ICSBEP is discussed in this paper, and the future of the two projects is outlined and discussed. Selected benchmarks that have been added to the IRPhEP and ICSBEP handbooks since PHYSOR-06 are highlighted, and the future of the two projects is discussed

1st International Conference on Engineering and Applied Sciences Optimization : Dedicated to the Memory of Professor M.G. Karlaftis

CERN Document Server

Papadrakakis, Manolis; OPT-i

2015-01-01

The chapters which appear in this volume are selected studies presented at the First International Conference on Engineering and Applied Sciences Optimization (OPT-i), Kos, Greece, 4-6 June 2014,  and works written by friends, former colleagues and students of the late Professor M. G. Karlaftis; all in the area of optimization that he loved and published so much in himself. The subject areas represented here range from structural optimization, logistics, transportation, traffic and telecommunication networks to operational research, metaheuristics, multidisciplinary and multiphysics design optimization, etc.  This volume is dedicated to the life and the memory of Professor Matthew G. Karlaftis, who passed away a few hours before he was to give the opening speech at OPT-i. All contributions reflect the warmth and genuine friendship which he enjoyed from his associates and show how much his scientific contribution has been appreciated. He will be greatly missed and it is hoped that this volume will be receive...

Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

Application of patient safety indicators internationally: a pilot study among seven countries

OpenAIRE

Drösler, Saskia E.; Klazinga, Niek S.; Romano, Patrick S.; Tancredi, Daniel J.; Gogorcena Aoiz, Maria A.; Hewitt, Moira C.; Scobie, Sarah; Soop, Michael; Wen, Eugene; Quan, Hude; Ghali, William A.; Mattke, Soeren; Kelley, Edward

2017-01-01

Objective To explore the potential for international comparison of patient safety as part of the Health Care Quality Indicators project of the Organization for Economic Co-operation and Development (OECD) by evaluating patient safety indicators originally published by the US Agency for Healthcare Research and Quality (AHRQ). Design A retrospective cross-sectional study. Setting Acute care hospitals in the USA, UK, Sweden, Spain, Germany, Canada and Australia in 2004 and 2005/2006. Data source...

Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group

International Nuclear Information System (INIS)

2002-01-01

This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

[Patient safety in home care - A review of international recommendations].

Science.gov (United States)

Czakert, Judith; Lehmann, Yvonne; Ewers, Michael

2018-06-08

In recent years there has been a growing trend towards nursing care at home in general as well as towards intensive home care being provided by specialized home care services in Germany. However, resulting challenges for patient safety have rarely been considered. Against this background we aimed to explore whether international recommendations for patient safety in home care in general and in intensive home care in particular already exist and how they can stimulate further practice development in Germany. A review of online English documents containing recommendations for patient safety in intensive home care was conducted. Available documents were analyzed and compared in terms of their form and content. Overall, a small number of relevant documents could be identified. None of these documents exclusively refer to the intensive home care sector. Despite their differences, however, the analysis of four selected documents showed similarities, e. g., regarding specific topics of patient safety (communication, involvement of patients and their relatives, risk assessment, medication management, qualification). Furthermore, strengths and weaknesses of the documents became apparent: e. g., an explicit understanding of patient safety, a literature-based introduction to safety topics or an adaptation of the recommendations to the specific features of home care were occasionally lacking. This document analysis provides interesting input to the formal and content-related development of specific recommendations and to practice development in Germany to improve patient safety in home care. Copyright © 2018. Published by Elsevier GmbH.

Keynote speaker Col. Fitch talks to employee audience at Super Safety and Health Day at KSC.

Science.gov (United States)

1999-01-01

Capt. Dennis E. Fitch, a consultant and former pilot instructor with United Airlines, addresses an audience of KSC employees to kick off Super Safety and Health Day at KSC. Fitch related his tale of the catastrophic engine failure in UAL flight 232, which crash landed in Iowa in 1989, and the teamwork that contributed to his survival and the lives of 183 other passengers. For the second time Kennedy Space Center dedicated an entire day to safety and health. Most normal work activities were suspended to allow personnel to attend Super Safety and Health Day activities. The theme, 'Safety and Health Go Hand in Hand,' emphasized KSC's commitment to place the safety and health of the public, astronauts, employees and space-related resources first and foremost. Events also included a panel session about related issues, vendor exhibits, and safety training in work groups. The keynote address and panel session were also broadcast internally over NASA television.

International Fatigue Risk Management Forum : Safety Promotion and Feedback in FRMS

NARCIS (Netherlands)

Stewart, S.; Koornneef, F.; Akselsson, R.

2009-01-01

Chapter 8: International Fatigue Risk Management Forum - Safety Promotion and Feedback in FRMS The European Commission HILAS project (Human Integration into the Lifecycle of Aviation Systems - a project supported by the European Commission’s 6th Framework between 2005-2009) was focused on using

Safety culture for engineering companies. Licensing and design bases for Cofrentes NPP

International Nuclear Information System (INIS)

Nhorte Gomez, M.D.

1994-01-01

Safety culture must be given higher priority by all organisations. It must not be considered a separate concept, attributable to just one particular organisation, or a single responsible party. It is important to apply this criterion throughout the different phases of a nuclear power plant project (design, construction, commissioning and operation) without becoming isolated or dissociated. Nevertheless, it is absolutely essential to apply and consider it during operation, so to ensure highest possible safety standards. Consideration must also be given to the interfaces and interconnections between the different parties involved in the project (Owner of the NPP, Main Engineering Company, Main Supplier, Regulatory Body, etc) to build a SAFETY CULTURE in a collective and effective way. In applying the safety culture, an engineering company emphasises the following concepts: - Personal dedication and sense of responsibility in all those involved in any activity related to the safety of Nuclear Power Plants. - Clearly defined and readily accessible areas of responsibility and channels of communication - Strict adherence to procedures - Internal review of activities (Design review) (Author)

Historical aspects of meetings, publication series, and digital resources dedicated to echinoderms

Directory of Open Access Journals (Sweden)

Alexander Ziegler

2014-03-01

Full Text Available Half a century after the first scientific meeting dedicated to marine spiny-skinned animals (Deuterostomia: Echinodermata was held in Washington, DC, we take this opportunity to provide information on a number of historical aspects related to the echinoderm scientific community. Apart from shedding light on the historical origins of modern echinoderm conferences, the present contribution presents photographs taken during the first meeting of echinoderm researchers in 1963 as well as during the first installments of the International Echinoderm Conference and the European Conference on Echinoderms. Furthermore, we provide background information on publication series dedicated solely to the Echinodermata as well as descriptions of selected digital resources that focus on echinoderms. Finally, we present a number of echinoderm conference logos and flyers in addition to selected information about specific echinoderm meetings.

46 CFR 2.01-25 - International Convention for Safety of Life at Sea, 1974.

Science.gov (United States)

2010-10-01

... Inspection, will issue a completed Form CG-969, describing the passenger ship and certifying that an... TO THE PUBLIC VESSEL INSPECTIONS Inspecting and Certificating of Vessels § 2.01-25 International... certain passenger, cargo or tankships engaged in international voyages: (i) Passenger Ship Safety...

Improving battery safety by early detection of internal shorting with a bifunctional separator

Science.gov (United States)

Wu, Hui; Zhuo, Denys; Kong, Desheng; Cui, Yi

2014-10-01

Lithium-based rechargeable batteries have been widely used in portable electronics and show great promise for emerging applications in transportation and wind-solar-grid energy storage, although their safety remains a practical concern. Failures in the form of fire and explosion can be initiated by internal short circuits associated with lithium dendrite formation during cycling. Here we report a new strategy for improving safety by designing a smart battery that allows internal battery health to be monitored in situ. Specifically, we achieve early detection of lithium dendrites inside batteries through a bifunctional separator, which offers a third sensing terminal in addition to the cathode and anode. The sensing terminal provides unique signals in the form of a pronounced voltage change, indicating imminent penetration of dendrites through the separator. This detection mechanism is highly sensitive, accurate and activated well in advance of shorting and can be applied to many types of batteries for improved safety.

Labor-Management Cooperation in Illinois: How a Joint Union Company Team Is Improving Facility Safety.

Science.gov (United States)

Mahan, Bruce; Maclin, Reggie; Ruttenberg, Ruth; Mundy, Keith; Frazee, Tom; Schwartzkopf, Randy; Morawetz, John

2018-01-01

This study of Afton Chemical Corporation's Sauget facility and its International Chemical Workers Union Council (ICWUC) Local 871C demonstrates how significant safety improvements can be made when committed leadership from both management and union work together, build trust, train the entire work force in U.S. Occupational Safety and Health Administration 10-hour classes, and communicate with their work force, both salaried and hourly. A key finding is that listening to the workers closest to production can lead to solutions, many of them more cost-efficient than top-down decision-making. Another is that making safety and health an authentic value is hard work, requiring time, money, and commitment. Third, union and management must both have leadership willing to take chances and learn to trust one another. Fourth, training must be for everyone and ongoing. Finally, health and safety improvements require dedicated funding. The result was resolution of more than one hundred safety concerns and an ongoing institutionalized process for continuing improvement.

75 FR 3471 - International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the...

Science.gov (United States)

2010-01-21

...] International Conference on Harmonisation; Guidance on M3(R2) Nonclinical Safety Studies for the Conduct of... the availability of a guidance entitled ``M3(R2) Nonclinical Safety Studies for the Conduct of Human... auspices of the International Conference on Harmonisation of Technical Requirements for Registration of...

IAEA/SiP senior managers workshop on international promotion of safety culture for the NPPs with RBMK reactors. Working material

International Nuclear Information System (INIS)

1996-01-01

The IAEA/SiP Senior Managers Workshop on International Promotion of Safety Culture for the NPPs with RMBK reactors was organized in the frame of the IAEA Technical Cooperation Regional Project RER/9/035 and the IAEA Extrabudgetary Project on WWER and RBMK Safety in co-operation with Swedish International Project Nuclear Safety (SiP). It took place at the Forsmark NPP, Sweden, from 1 to 4 October 1996. The objectives of the workshop were to provide a forum for senior managers to exchange national and international experience on factors influencing safety culture, to better understand these factors and to further enhance promotion of safety culture. Twenty-three specialists participated in the workshop from six countries (Canada, Lithuania, Russian Federation, Sweden, Ukraine and USA) and from two international organizations (WANO, EC-G24 coordination). Participants were from regulatory bodies, ministries and operational organizations of respective countries. The INSAG-4 definition of safety culture was taken as a starting point for the discussions, but at the start of the workshop participants did not seem to have the same understanding of what is contained in the safety culture context. Specifically the difference between measures taken to improve safety and establishing a proper safety culture level was discussed with useful results. Some participants proposed quantitative safety culture indicators, but there was no agreement at this stage about how to define them. Refs

IAEA/SiP senior managers workshop on international promotion of safety culture for the NPPs with RBMK reactors. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The IAEA/SiP Senior Managers Workshop on International Promotion of Safety Culture for the NPPs with RMBK reactors was organized in the frame of the IAEA Technical Cooperation Regional Project RER/9/035 and the IAEA Extrabudgetary Project on WWER and RBMK Safety in co-operation with Swedish International Project Nuclear Safety (SiP). It took place at the Forsmark NPP, Sweden, from 1 to 4 October 1996. The objectives of the workshop were to provide a forum for senior managers to exchange national and international experience on factors influencing safety culture, to better understand these factors and to further enhance promotion of safety culture. Twenty-three specialists participated in the workshop from six countries (Canada, Lithuania, Russian Federation, Sweden, Ukraine and USA) and from two international organizations (WANO, EC-G24 coordination). Participants were from regulatory bodies, ministries and operational organizations of respective countries. The INSAG-4 definition of safety culture was taken as a starting point for the discussions, but at the start of the workshop participants did not seem to have the same understanding of what is contained in the safety culture context. Specifically the difference between measures taken to improve safety and establishing a proper safety culture level was discussed with useful results. Some participants proposed quantitative safety culture indicators, but there was no agreement at this stage about how to define them. Refs.

The Nuclear Safety Convention - does it confirm existing German law, and update international law?

International Nuclear Information System (INIS)

Lindemann, C.

1995-01-01

Some selected examples are discussed that are intended to answer the question of whether the NSC in its essence represents a development in confirmation of existing German nuclear law, and whether, assuming its coming into effect, this Convention will mean a step forward in the development of international law. The author examines the value of this codification of international law as such, and some of the obligations and standards such as retrofitting measures or shutdown of reactors below safety standard, and continues with briefly discussing the relationship between the NSC and nuclear liability law, the planned provisions for radiological protection in Art. 15, and the obligations for transboundary notification of safety-relevant events. These stipulations are analysed in comparison to existing international law, and with a view to their implementation under German law. Some provisions of the NSC that are based on standards of international technical guidance are compared with German regulatory guides. (orig./HP) [de

The Ninth International scientific and technical conference Safety, efficiency and economy of atomic energy. Book of abstracts

International Nuclear Information System (INIS)

2014-01-01

The abstracts of the Ninth International scientific and technical conference Safety, efficiency and economy of atomic energy are present. The conference took place in Moscow, 21-23 May, 2014. The problems of WWER, RBMK, BN and EhGP-6 NPPs operation, maintenance and repair; materials testing and metallic structures control; radioactive wastes and spent fuel management; NPP decommissioning; radiation safety, NPP ecology, emergency preparedness were discussed on the conference. The great attention was paid to the problems of atomic energy economy and its developing, international cooperation for NPP safety and young NPP specialists training [ru

Feasibility analysis of the Primary Loop of Pool-Type Natural Circulating Nuclear Reactor Dedicated to Seawater Desalination

Energy Technology Data Exchange (ETDEWEB)

Jeong, Woonho; Jeong, Yong Hoon [KAIST, Daejeon (Korea, Republic of)

2016-05-15

In this study, the feasibility of natural circulation was evaluated for the reference plant AHR400 (Advanced Heating Reactor 400MWth). AHR400 is a pool-type desalination-dedicated nuclear reactor. As a consequence, AHR400 has low operating pressure and temperature which provides large safety margin. Removal of the reactor coolant pump from the AHR400 will enforce integrity of the reactor vessel and passive safety feature. Therefore, the study also tried to find out optimized primary loop design to achieve total natural circulation of the coolant. Natural circulation capacity of the primary loop of the desalination dedicated nuclear reactor AHR400 was evaluated. It was concluded that to remove RCP from the AHR400 and operates the reactor only by natural circulation of the coolant is impossible. Decreased core power as half make removal of RCP possible with 15m central height difference between the core and IHXs. Furthermore, validation and modification of pressure loss coefficients by small-scaled natural circulation experiment at a pool-type reactor would provide more accurate results.

International demands for retrofitting, trends in the nuclear industry, safety margins, concepts and options for retrofit; Nachfrage nach Nachruestungen international; industrielle Trends; Rolle von Sicherheitsmargen, Nachruestkonzepte und -moeglichkeiten

Energy Technology Data Exchange (ETDEWEB)

Janke, Rolf; Stoll, Uwe; Grasnick, Claudius [AREVA GmbH, Erlangen (Germany). E and P, P-G

2016-02-15

The serious accidents at Fukushima in 2011 pointed out the missing implementation of existing international safety standards for nuclear power plants as also new aspects for nuclear safety. The main safety aspects in the aftermath of Fukushima are: robustness against internal and external impacts; sufficient safety margins; prolonged periods for safety measures; inherent and passive systems and mechanisms; enhanced independent operation of the plant in case of external failures; independent long-term supply with AC; accident management procedures; enhanced retention of radionuclides. Technologies for retrofit are available and are under implementation with respect to the demands and options in the countries using nuclear power.

Gas-cooled fast reactor safety - and overview and status of the U.S. program

International Nuclear Information System (INIS)

Torri, A.; Buttemer, D.R.

1981-01-01

In the revised GCFR Safety Program Plan a quantitative risk limit line has been adopted to establish requirements for the safety related functions and systems. The risk limit line is derived from an interpretation of NRC established licensing requirements, including those for LMFBR's. Multiple barriers to the progression of accident sequences are defined in the form of six Lines of Protection (LOPs). LOPs-1 to 3 are dedicated to accident prevention and represent the normal operating systems, the dedicated safety systems and the inherent design features, respectively. LOPs-4 to 6 are dedicated to the mitigation of core melt accident consequences and include in-vessel accident containment, secondary containment integrity and radiological attenuation, respectively. Cumulative frequency limits and consequence limits are established for each LOP. Design features associated with each LOP are described and the results of supporting safety analyses are summarized. (author)

Optical Design Using Small Dedicated Computers

Science.gov (United States)

Sinclair, Douglas C.

1980-09-01

Since the time of the 1975 International Lens Design Conference, we have developed a series of optical design programs for Hewlett-Packard desktop computers. The latest programs in the series, OSLO-25G and OSLO-45G, have most of the capabilities of general-purpose optical design programs, including optimization based on exact ray-trace data. The computational techniques used in the programs are similar to ones used in other programs, but the creative environment experienced by a designer working directly with these small dedicated systems is typically much different from that obtained with shared-computer systems. Some of the differences are due to the psychological factors associated with using a system having zero running cost, while others are due to the design of the program, which emphasizes graphical output and ease of use, as opposed to computational speed.

Assistance of Foreign Countries and International Organizations to Support Safety Improvements at Ignalina NPP

International Nuclear Information System (INIS)

Shevaldin, V.

1997-01-01

International cooperation and assistance for the improving safety of Ignalina NPP is described. Sweden was among the first countries which supported safety improvements at Ignalina NPP. The first project in the cooperation was BARSELINA, Probabilistic Safety Analysis of Ignalina NPP. The cooperation is still bringing significant support to the plant, including improvements in the fire protection, communications system, physical protection, and many other areas. Another one very important source of assistance was Nuclear Safety Account, administered by the EBRD. In 1993 experts of the plant, together with representatives of VATESI and SKI (Sweden) have worked out a short-term safety improvement program SIP-1, which was financed by the EBRD . Eighteen safety related projects were selected, expensive and reliable equipment was procured and installed

Utilizing the Fast Flux Test Facility for international passive safety testing

International Nuclear Information System (INIS)

Shen, P.K.; Padilla, A.; Lucoff, D.M.; Waltar, A.E.

1991-01-01

A two-phased approach has been undertaken in the Fast Flux Test Facility (FFTF) to conduct passive safety testing. Phase I (1986 to 1987) was structured to obtain an initial understanding of the reactivity feedback components. The planned Phase II (1992 to 1993) international program will extend the testing to include static and dynamic feedback measurements, transient and demonstration tests, and gas expansion module (GEM) reactivity tests. The primary objective is to meet the needs for safety analysis code validation, with particular emphasis on reducing the uncertainties associated with structure reactivity feedback. Program scope and predicted FFTF responses are discussed and illustrated. (author)

Dedication increases productivity: an analysis of the implementation of a dedicated medical team in the emergency department.

Science.gov (United States)

Ramos, Pedro; Paiva, José Artur

2017-12-01

In several European countries, emergency departments (EDs) now employ a dedicated team of full-time emergency medicine (EM) physicians, with a distinct leadership and bed-side emergency training, in all similar to other hospital departments. In Portugal, however, there are still two very different models for staffing EDs: a classic model, where EDs are mostly staffed with young inexperienced physicians from different medical departments who take turns in the ED in 12-h shifts and a dedicated model, recently implemented in some hospitals, where the ED is staffed by a team of doctors with specific medical competencies in emergency medicine that work full-time in the ED. Our study assesses the effect of an intervention in a large academic hospital ED in Portugal in 2002, and it is the first to test the hypothesis that implementing a dedicated team of doctors with EM expertise increases the productivity and reduces costs in the ED, maintaining the quality of care provided to patients. A pre-post design was used for comparing the change on the organisational model of delivering care in our medical ED. All emergency medical admissions were tracked in 2002 (classic model with 12-h shift in the ED) and 2005/2006 (dedicated team with full-time EM physicians), and productivity, costs with medical human resources and quality of care measures were compared. We found that medical productivity (number of patients treated per hour of medical work) increased dramatically after the creation of the dedicated team (X 2 KW = 31.135; N = 36; p work reduced both in regular hours and overtime. Moreover, hospitalisation rates decreased and the length of stay in the ED increased significantly after the creation of the dedicated team. Implementing a dedicated team of doctors increased the medical productivity and reduced costs in our ED. Our findings have straightforward implication for Portuguese policymakers aiming at reducing hospital costs while coping with increased ED demand.

A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Carvalho, Jose Antonio B.; Saldanha, Pedro L.C. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao-Geral de Reatores e Ciclo Combustivel], e-mail: jantonio@cnen.gov.br, e-mail: saldanha@cnen.gov.br; Melo, Paulo F.F. Frutuoso e [Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear], e-mail: frutuoso@con.ufrj.br

2009-07-01

Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

International Nuclear Information System (INIS)

Carvalho, Jose Antonio B.; Saldanha, Pedro L.C.; Melo, Paulo F.F. Frutuoso e

2009-01-01

Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

Safety of Long-term Interim Storage Facilities - Workshop Proceedings

International Nuclear Information System (INIS)

2014-01-01

The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided as well as a summary of the results of the workshop with the text of the papers given and presentations made

Identifying research priorities for patient safety in mental health: an international expert Delphi study

Science.gov (United States)

Murray, Kevin; Thibaut, Bethan; Ramtale, Sonny Christian; Adam, Sheila; Darzi, Ara; Archer, Stephanie

2018-01-01

Objective Physical healthcare has dominated the patient safety field; research in mental healthcare is not as extensive but findings from physical healthcare cannot be applied to mental healthcare because it delivers specialised care that faces unique challenges. Therefore, a clearer focus and recognition of patient safety in mental health as a distinct research area is still needed. The study aim is to identify future research priorities in the field of patient safety in mental health. Design Semistructured interviews were conducted with the experts to ascertain their views on research priorities in patient safety in mental health. A three-round online Delphi study was used to ascertain consensus on 117 research priority statements. Setting and participants Academic and service user experts from the USA, UK, Switzerland, Netherlands, Ireland, Denmark, Finland, Germany, Sweden, Australia, New Zealand and Singapore were included. Main outcome measures Agreement in research priorities on a five-point scale. Results Seventy-nine statements achieved consensus (>70%). Three out of the top six research priorities were patient driven; experts agreed that understanding the patient perspective on safety planning, on self-harm and on medication was important. Conclusions This is the first international Delphi study to identify research priorities in safety in the mental field as determined by expert academic and service user perspectives. A reasonable consensus was obtained from international perspectives on future research priorities in patient safety in mental health; however, the patient perspective on their mental healthcare is a priority. The research agenda for patient safety in mental health identified here should be informed by patient safety science more broadly and used to further establish this area as a priority in its own right. The safety of mental health patients must have parity with that of physical health patients to achieve this. PMID:29502096

Low-frequency electrical dosimetry: research agenda of the IEEE International Committee on Electromagnetic Safety.

Science.gov (United States)

Reilly, J Patrick; Hirata, Akimasa

2016-06-21

This article treats unsettled issues in the use of numerical models of electrical dosimetry as applied to international limits on human exposure to low-frequency (typically  IEEE-ICES (International Committee on Electromagnetic Safety) Technical Committee 95. The paper discusses 25 issues needing attention, fitting into three general categories: induction models; electrostimulation models; and human exposure limits. Of these, 9 were voted as 'high priority' by members of Subcommittee 6. The list is presented as a research agenda for refinements in numerical modeling with applications to human exposure limits. It is likely that such issues are also important in medical and electrical product safety design applications.

Towards a new international framework for nuclear safety: Developments from Fukushima to Vienna

International Nuclear Information System (INIS)

Durand-Poudret, Emma

2015-01-01

On 11 March 2011, the nuclear safety sector was deeply shaken by the accident at the Fukushima Daiichi nuclear power plant in Japan. Because of this accident, 25 years of established certainties in nuclear power plant operational safety that followed the Chernobyl disaster were once again called into question. The adequacy of the international safety instruments was naturally questioned as well. The global nuclear safety framework is primarily composed of the Convention on Nuclear Safety (CNS) and the safety standards of the International Atomic Energy Agency (IAEA). Should this accident have been an inducement for a comprehensive overhaul of the existing framework? The broader international community mobilised its resources in response to this event, reflecting the overriding importance of nuclear safety and the urgent need to learn lessons from the accident. A process of reviewing the effectiveness of the CNS thus began in April 2011 at the Fifth Review Meeting of the Contracting Parties to the Convention. In September 2011, the adoption of the IAEA Action Plan on Nuclear Safety encouraged the states parties to study mechanisms to enhance the effective implementation of the CNS and to consider proposals to amend the Convention. In August 2012, the Second Extraordinary Meeting of the Contracting Parties allowed certain states to table amendments, thus stimulating debate but also revealing the difficulty of obtaining the majority required for such an undertaking. In order to break the impasse, an effectiveness and transparency working group was set up with the ambitious task of reporting to the Sixth Review Meeting on 'a list of actions to strengthen the CNS and on proposals to amend, where necessary, the Convention'. Since the amendment approach appeared to be a valid solution, Switzerland took the opportunity of the Sixth Review Meeting to submit a new draft to that effect. The convening of a Diplomatic Conference under Article 32 of the CNS would then

Comment on the internal consistency of thermodynamic databases supporting repository safety assessments

International Nuclear Information System (INIS)

Arthur, R.C.

2001-11-01

This report addresses the concept of internal consistency and its relevance to the reliability of thermodynamic databases used in repository safety assessments. In addition to being internally consistent, a reliable database should be accurate over a range of relevant temperatures and pressures, complete in the sense that all important aqueous species, gases and solid phases are represented, and traceable to original experimental results. No single definition of internal consistency need to be universally accepted as the most appropriate under all conditions, however. As a result, two databases that are each internally consistent may be inconsistent with respect to each other, and a database derived from two or more such databases must itself be internally inconsistent. The consequences of alternative definitions that are reasonably attributable to the concept of internal consistency can be illustrated with reference to the thermodynamic database supporting SKB's recent SR 97 safety assessment. This database is internally inconsistent because it includes equilibrium constants calculated over a range of temperatures: using conflicting reference values for some solids, gases and aqueous species that are common to two internally consistent databases (the OECD/NEA database for radioelements and SUPCRT databases for non-radioactive elements) that serve as source databases for the SR 97 TDB, using different definitions in these source databases of standard states for condensed phases and aqueous species, based on different mathematical expressions used in these source databases representing the temperature dependence of the heat capacity, and based on different chemical models adopted in these source databases for the aqueous phase. The importance of such inconsistencies must be considered in relation to the other database reliability criteria noted above, however. Thus, accepting a certain level of internal inconsistency in a database it is probably preferable to use a

Comment on the internal consistency of thermodynamic databases supporting repository safety assessments

Energy Technology Data Exchange (ETDEWEB)

Arthur, R.C. [Monitor Scientific, LLC, Denver, CO (United States)

2001-11-01

This report addresses the concept of internal consistency and its relevance to the reliability of thermodynamic databases used in repository safety assessments. In addition to being internally consistent, a reliable database should be accurate over a range of relevant temperatures and pressures, complete in the sense that all important aqueous species, gases and solid phases are represented, and traceable to original experimental results. No single definition of internal consistency need to be universally accepted as the most appropriate under all conditions, however. As a result, two databases that are each internally consistent may be inconsistent with respect to each other, and a database derived from two or more such databases must itself be internally inconsistent. The consequences of alternative definitions that are reasonably attributable to the concept of internal consistency can be illustrated with reference to the thermodynamic database supporting SKB's recent SR 97 safety assessment. This database is internally inconsistent because it includes equilibrium constants calculated over a range of temperatures: using conflicting reference values for some solids, gases and aqueous species that are common to two internally consistent databases (the OECD/NEA database for radioelements and SUPCRT databases for non-radioactive elements) that serve as source databases for the SR 97 TDB, using different definitions in these source databases of standard states for condensed phases and aqueous species, based on different mathematical expressions used in these source databases representing the temperature dependence of the heat capacity, and based on different chemical models adopted in these source databases for the aqueous phase. The importance of such inconsistencies must be considered in relation to the other database reliability criteria noted above, however. Thus, accepting a certain level of internal inconsistency in a database it is probably preferable to

International Nuclear Safety Experts Conclude IAEA Peer Review of Korea's Regulatory System

International Nuclear Information System (INIS)

2011-01-01

Full text: An international team of senior nuclear safety experts concluded today a two-week mission to review the regulatory framework for nuclear safety in the Republic of Korea. The team identified good practices and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of Korea, while the final report will be submitted by the end of summer 2011. At the request of the Korean Government, the IAEA assembled a team of 16 senior regulatory experts from 14 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Korean Ministry for Education, Science and Technology (MEST) and the Korean Institute for Nuclear Safety (KINS). The mission is a peer-review based on the IAEA Safety Standards. ''This was the first IRRS mission organized after Japan's Fukushima Daiichi nuclear accident and it included a review of the regulatory implications of that event,' explains Denis Flory, IAEA Deputy Director General and Head of the Department of Nuclear Safety and Security. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission and Team Leader of this mission commended the Korean authorities for their openness and commitment to sharing their experience with the world's nuclear safety community. ''IRRS missions such as the one that was just concluded here in the Republic of Korea are crucial to the enhancement of nuclear safety worldwide,'' he said. The IRRS team reviewed Korea's current regulatory framework while acknowledging the fact that the country's Government has already decided to establish, as of October 2011, a new independent regulatory body to be called Nuclear Safety Commission (NSC). As a consequence, KINS role will be as a regulatory expert organization reporting to the NSC, while MEST's role will be restricted to promoting the utilization of nuclear energy. The IRRS team identified particular strengths in the Korean regulatory system

Research Tool to Evaluate the Safety Response of Lithium Batteries to an Internal Short Circuit

Energy Technology Data Exchange (ETDEWEB)

Keyser, Matthew; Darcy, Eric; Pesaran, Ahmad

2016-06-19

Li-ion cells provide the highest specific energy and energy density rechargeable battery with the longest life. Many safety incidents that take place in the field originate due to an internal short that was not detectable or predictable at the point of manufacture. NREL's internal short circuit (ISC) device is capable of simulating shorts and produces consistent and reproducible results. The cell behaves normally until the ISC device is activated wherein a latent defect (i.e., built into the cell during manufacturing) gradually moves into position to create an internal short while the battery is in use, providing relevant data to verify abuse models. The ISC device is an effective tool for studying the safety features of parts of Li-ion batteries.

Major food safety episodes in Taiwan: implications for the necessity of international collaboration on safety assessment and management.

Science.gov (United States)

Li, Jih-Heng; Yu, Wen-Jing; Lai, Yuan-Hui; Ko, Ying-Chin

2012-07-01

The major food safety episodes that occurred in Taiwan during the past decade are briefly reviewed in this paper. Among the nine major episodes surveyed, with the exception of a U.S. beef (associated with Creutzfeldt-Jakob disease)-related incident, all the others were associated with chemical toxicants. The general public, which has a layperson attitude of zero tolerance toward food safety, may panic over these food-safety-associated incidents. However, the health effects and impacts of most incidents, with the exception of the melamine incident, were essentially not fully evaluated. The mass media play an important role in determining whether a food safety concern becomes a major incident. A well-coordinated and harmonized system for domestic and international collaboration to set up standards and regulations is critical, as observed in the incidents of pork with ractopamine, Chinese hairy crab with nitrofuran antibiotics, and U.S. wheat with malathion. In the future, it can be anticipated that food safety issues will draw more attention from the general public. For unknown new toxicants or illicit adulteration of food, the establishment of a more proactive safety assessment system to monitor potential threats and provide real-time information exchange is imperative. Copyright © 2012. Published by Elsevier B.V.

Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

International Nuclear Information System (INIS)

2014-01-01

The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-10) in Okinawa, Japan is sponsored by Atomic Energy Society of Japan, in cooperation with the International Atomic Energy Agency, and co-sponsored by American Nuclear Society Thermal Hydraulics Division among others. Enhanced safety and reducing cost are going together, which can be achieved through continued research and development efforts. NUTHOS keeps you abreast of the most updated information in the advancement of science and technology in nuclear thermal hydraulics, operations and safety, and provides you insights into the future. (J.P.N.)

A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

International Nuclear Information System (INIS)

Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil

1990-12-01

The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea

A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

Energy Technology Data Exchange (ETDEWEB)

Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1990-12-15

The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea.

Dedicated radial ventriculography pigtail catheter

Energy Technology Data Exchange (ETDEWEB)

Vidovich, Mladen I., E-mail: miv@uic.edu

2013-05-15

A new dedicated cardiac ventriculography catheter was specifically designed for radial and upper arm arterial access approach. Two catheter configurations have been developed to facilitate retrograde crossing of the aortic valve and to conform to various subclavian, ascending aortic and left ventricular anatomies. The “short” dedicated radial ventriculography catheter is suited for horizontal ascending aortas, obese body habitus, short stature and small ventricular cavities. The “long” dedicated radial ventriculography catheter is suited for vertical ascending aortas, thin body habitus, tall stature and larger ventricular cavities. This new design allows for improved performance, faster and simpler insertion in the left ventricle which can reduce procedure time, radiation exposure and propensity for radial artery spasm due to excessive catheter manipulation. Two different catheter configurations allow for optimal catheter selection in a broad range of patient anatomies. The catheter is exceptionally stable during contrast power injection and provides equivalent cavity opacification to traditional femoral ventriculography catheter designs.

The International Atomic Energy Agency (IAEA) standards and recommendations on radioactive waste and transport safety

International Nuclear Information System (INIS)

Warnecke, E.; Rawl, R.

1996-01-01

The International Atomic Energy Agency (IAEA) publishes standards and recommendations on all aspects of nuclear safety in its Safety Series, which includes radioactive waste management and transport of radioactive materials. Safety Series documents may be adopted by a State into its national legal framework. Most of the States used the IAEA transport regulations (Safety Series No. 6) as a basis for their national regulation. The two highest ranking documents of the Radioactive Waste Safety Standards (RADWASS) programme, the Safety Fundamentals and the Safety Standard on the national waste management system, have been published. Both provide impetus into the waste management safety convention, a legally binding document for signatory states, which is being drafted. The already existing Convention on Nuclear Safety covers the management of radioactive waste at land-based civil nuclear power plants. (author) 1 fig., 18 refs

Safety of nuclear installations. An international comparison

International Nuclear Information System (INIS)

Renner, Andrea; Diwes, Andreas; Reingardt, Martin

2010-01-01

Safeguarding of nuclear power plants against disruptive actions or other external hazards is part of the plant design and presumption of an operation license. The general principle is defense in depth involving different security zones with separate barriers. The safeguards for nuclear installations are organized in three areas of responsibility: governmental measures (police, military), technical (detectors, scanners, illuminations, camera tracking, concrete barriers) and personnel measures (access control, security personnel, alarm) of the operating company. International responsibilities results from the treaty on the non-proliferation of nuclear weapons and several IAEA documents. The authors discuss the national regulations in Germany, Switzerland, United Kingdom and USA. Older NPPs that are not in compliance with actual safety standards will be a topic of increasing importance.

IAEA Sets Up Team to Drive Nuclear Safety Action Plan

International Nuclear Information System (INIS)

2011-01-01

Full text: The International Atomic Energy Agency is setting up a Nuclear Safety Action Team to oversee prompt implementation of the IAEA Action Plan on Nuclear Safety and ensure proper coordination among all stakeholders. The 12-point Action Plan, drawn up in the wake of the Fukushima Daiichi accident, was approved by the Agency's Board of Governors on 13 September and endorsed by all 151 Member States at its General Conference last week. The team will work within the Agency's Department of Nuclear Safety and Security, headed by Deputy Director General Denis Flory, and will coordinate closely with the Director General's Office for Policy. ''The Action Plan requires immediate follow-up,'' Director General Yukiya Amano said. ''This compact, dedicated team will assist Deputy Director General Flory in implementing the measures agreed in the Action Plan.'' Gustavo Caruso, Head of the Regulatory Activities Section in the IAEA's Division of Installation Safety, has been designated as the team's Special Coordinator for the implementation of the Action Plan. The IAEA has already started implementing its responsibilities under the Action Plan, including development of an IAEA methodology for stress tests for nuclear power plants. The methodology will be ready in October. (IAEA)

Discussion on building safety culture inside a nuclear safety regulatory body

International Nuclear Information System (INIS)

Fan Yumao

2013-01-01

A strong internal safety culture plays a key role in improving the performance of a nuclear regulatory body. This paper discusses the definition of internal safety culture of nuclear regulatory bodies, and explains the functions that the safety culture to facilitate the nuclear safety regulation and finally puts forward some thoughts about building internal safety culture inside regulatory bodies. (author)

Basic safety standards for radiation protection and their application to internal exposures

International Nuclear Information System (INIS)

Dousset, M.

Following a summary of the basic concepts on radiation protection units, the safety standards now in effect in France and those recommended by the International Commission on Radiological Protection (ICRP Publication 9, 1965) to be used as a basis to the next Euratom regulations are developed [fr

7T: Physics, safety, and potential clinical applications.

Science.gov (United States)

Kraff, Oliver; Quick, Harald H

2017-12-01

With more than 60 installed magnetic resonance imaging (MRI) systems worldwide operating at a magnetic field strength of 7T or higher, ultrahigh-field (UHF) MRI has been established as a platform for clinically oriented research in recent years. Profound technical and methodological developments have helped overcome the inherent physical challenges of UHF radiofrequency (RF) signal homogenization in the human body. The ongoing development of dedicated RF coil arrays was pivotal in realizing UHF body MRI, beyond mere brain imaging applications. Another precondition to clinical application of 7T MRI is the safety testing of implants and the establishment of safety concepts. Against this backdrop, 7T MRI and MR spectroscopy (MRS) recently have demonstrated capabilities and potentials for clinical diagnostics in a variety of studies. This article provides an overview of the immanent physical challenges of 7T UHF MRI and discusses recent technical solutions and safety concepts. Furthermore, recent clinically oriented studies are highlighted that span a broad application spectrum from 7T UHF brain to body MRI. 4 Technical Efficacy: Stage 1 J. Magn. Reson. Imaging 2017;46:1573-1589. © 2017 International Society for Magnetic Resonance in Medicine.

Speaking up about traditional and professionalism-related patient safety threats: a national survey of interns and residents.

Science.gov (United States)

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

2017-11-01

Open communication between healthcare professionals about care concerns, also known as 'speaking up', is essential to patient safety. Compare interns' and residents' experiences, attitudes and factors associated with speaking up about traditional versus professionalism-related safety threats. Anonymous, cross-sectional survey. Six US academic medical centres, 2013-2014. 1800 medical and surgical interns and residents (47% responded). Attitudes about, barriers and facilitators for, and self-reported experience with speaking up. Likelihood of speaking up and the potential for patient harm in two vignettes. Safety Attitude Questionnaire (SAQ) teamwork and safety scales; and Speaking Up Climate for Patient Safety (SUC-Safe) and Speaking Up Climate for Professionalism (SUC-Prof) scales. Respondents more commonly observed unprofessional behaviour (75%, 628/837) than traditional safety threats (49%, 410/837); pbarrier to speaking up about unprofessional behaviour compared with traditional safety threats (58%, 482/837 vs 42%, 348/837; psafety vignette, even when they perceived high potential patient harm (20%, 49/251 vs 71%, 179/251; psafety vignette (OR 1.90, 99% CI 1.36 to 2.66 and 1.46, 1.02 to 2.09, respectively), while only a positive perception of SUC-Prof was associated with speaking up in the professionalism vignette (1.76, 1.23 to 2.50). Interns and residents commonly observed unprofessional behaviour yet were less likely to speak up about it compared with traditional safety threats even when they perceived high potential patient harm. Measuring SUC-Safe, and particularly SUC-Prof, may fill an existing gap in safety culture assessment. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

Key practical issues in strengthening safety culture. INSAG-15. A report by the International Safety Advisory Group [Russian Edition

International Nuclear Information System (INIS)

2015-01-01

This report describes the essential practical issues to be considered by organizations aiming to strengthen safety culture. It is intended for senior executives, managers and first line supervisors in operating organizations. Although safety culture cannot be directly regulated, it is important that members of regulatory bodies understand how their actions affect the development of attempts to strengthen safety culture and are sympathetic to the need to improve the less formal human related aspects of safety. The report is therefore of relevance to regulators, although not intended primarily for them. The International Nuclear Safety Advisory Group (INSAG) introduced the concept of safety culture in its INSAG-4 report in 1991. Since then, many papers have been written on safety culture, as it relates to organizations and individuals, its improvement and its underpinning prerequisites. Variations in national cultures mean that what constitutes a good approach to enhancing safety culture in one country may not be the best approach in another. However, INSAG seeks to provide pragmatic and practical advice of wide applicability in the principles and issues presented in this report. Nuclear and radiological safety are the prime concerns of this report, but the topics discussed are so general that successful application of the principles should lead to improvements in other important areas, such as industrial safety, environmental performance and, in some respects, wider business performance. This is because many of the attitudes and practices necessary to achieve good performance in nuclear safety, including visible commitment by management, openness, care and thoroughness in completing tasks, good communication and clarity in recognizing major issues and dealing with them as a priority, have wide applicability

Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety

International Nuclear Information System (INIS)

1997-01-01

The fifth international topical meeting on nuclear thermohydraulics, operations and safety was convened in Beijing in April 14-18, 1997. The topical meeting was sponsored by the Chinese Nuclear Society and cosponsored by American Nuclear Society, Atomic Energy Society of Japan, American Society of Mechanical Engineers, Canada Nuclear Society, Korean Nuclear Society, Mexican Nuclear Society, Nuclear Society of Slovenia and Spanish Nuclear Society. There were 262 articles were published in the meeting. They are related nuclear power thermohydraulics, operations and safety

International cooperation in the safety and environmental assessment for the ITER engineering design activities

International Nuclear Information System (INIS)

Gordon, C.; Baker, D.J.; Bartels, H-W.

1998-01-01

The ITER Project includes design and assessment activities to ensure the safety and environmental attractiveness of ITER and demonstrate that it can be sited in any of the sponsoring Parties with a minimum of site-specific redesign. This paper highlights some of the efforts to develop an international consensus approach for ITER safety design and assessment, including: development of general safety and environmental design criteria; development of quantitative dose-release assessment criteria; development of a radiation protection program; waste characterization; and development of safety analysis guidelines. The high level of interaction, cooperation and collaboration between the Joint Central Team and the Home Teams, and between the safety team and designers, and the spirit of consensus that has guided them have resulted in a safe design for ITER and a safety design and assessment that can meet the needs of the potential host countries. (author)

International seminar on the safety research needs for Russian-designed reactors: material presented at the international seminar 1997

International Nuclear Information System (INIS)

1997-01-01

This seminar on international, national and bilateral cooperation programmes on the safety research needs for Russian-designed reactors was held in Tokyo, Japan (1997) and hosted by the OECD Nuclear Energy Agency and the Science and Technology Agency (STA) of Japan. More than 70 participants attended the seminar. Represented were experts from OECD/NEA member countries and Russia, the International Atomic Energy Agency (IAEA), the ISTC, the INSC and the Russian INSC. Eighteen papers were presented in five sessions. The seminar was structured around four main areas of cooperation: cooperative programmes of the OECD/NEA, programmes of international organisations, bi-lateral programmes, and national programmes of OECD/NEA member countries having reactors of the VVER type. General conclusions, followed by specific technical conclusions are included

The safety evaluation guide for laboratories and plants a tool for enhancing safety

International Nuclear Information System (INIS)

Lhomme, Veronique; Daubard, Jean-Paul

2013-01-01

The Institute for Radioprotection and Nuclear Safety (IRSN) acts as technical support for the French government Authorities competent in nuclear safety and radiation protection for civil and defence activities. In this frame, the Institute's performs safety assessments of the safety cases submitted by operators to these Authorities for each stage in the life cycle of a nuclear facility, including dismantling operations, which is subjected to a licensing procedure. In the fuel cycle field, this concerns a large variety of facilities. Very often, depending on facilities and on safety cases, safety assessment to be performed is multidisciplinary and involves the supervisor in charge of the facility and several safety experts, particularly to cover the whole set of risks (criticality, exposure to radiation, fire, handling, containment, human and organisational factors...) encountered during facility's operations. Taking these into account, and in order to formalize the assessment process of the fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management, the 'Plants, Laboratories, Transports and Waste Safety' Division of IRSN has developed an internal guide, as a tool: - To present the methodological framework, and possible specificities, for the assessment according to the 'Defence in Depth Concept' (Part 1); - To provide key questions associated to the necessary contradictory technical review of the safety cases (Part 2); - To capitalise on experience on the basis of technical examples (coming from incident reports, previous safety assessments...) demonstrating the questioning (Part 3). The guide is divided in chapters, each dedicated to a type of risk (dissemination of radioactive material, external or internal exposure from ionising radiation, criticality, radiolysis mechanisms, handling operations, earthquake, human or organisational factors...) or to a type

78 FR 28987 - Revisions to Transportation Safety Requirements and Harmonization With International Atomic...

Science.gov (United States)

2013-05-16

.... 115, ``International Basic Safety Standards for Protection against Ionizing Radiation and for the... paragraph 107(f) of TS-R-1, which addresses non-radioactive solid objects with radioactive substances..., ``Radiation protection--Sealed radioactive sources-- General requirements and classification,'' Second Edition...

Power electronic supply system with the wind turbine dedicated for average power receivers

Science.gov (United States)

Widerski, Tomasz; Skrzypek, Adam

2018-05-01

This article presents the original project of the AC-DC-AC converter dedicated to low power wind turbines. Such a set can be a good solution for powering isolated objects that do not have access to the power grid, for example isolated houses, mountain lodges or forester's lodges, where they can replace expensive diesel engine generators. An additional source of energy in the form of a mini-wind farm is also a good alternative to yachts, marinas and tent sites, which are characterized by relatively low power consumption. This article presents a designed low power wind converter that is dedicated to these applications. The main design idea of the authors was to create a device that converts the very wide range input voltage directly to a stable 230VAC output voltage without the battery buffer. Authors focused on maximum safety of using and service. The converter contains the thermal protection, short-circuit protection and overvoltage protection. The components have been selected in such a way as to ensure that the device functions as efficiently as possible.

Safe management of the operating lifetimes of nuclear power plants. INSAG-14. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

2014-01-01

The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. The present report by INSAG deals with a general approach to the safe management of the operating lifetimes of nuclear power plants. It responds to the concerns about maintaining adequate safety levels at ageing plants, even beyond their design lifetimes. Maintaining adequate safety levels implies first and foremost stringent control of equipment ageing, consistent with the design safety bases of the plants. However, as stated in the 75-INSAG-3 report, 'Basic Safety Principles for Nuclear Power Plants', nuclear safety requires a continuing quest for excellence; this implies enhancinuest for excellence; this implies enhancing the safety levels of operating nuclear power plants as far as reasonably practicable, with due account taken of experience and advancement in knowledge. Moreover, in view of the present situation of the nuclear industry, it may become difficult to maintain adequate competences in many countries with nuclear power programmes. These topics are considered in this latest INSAG report and released to a wider audience

Safe management of the operating lifetimes of nuclear power plants. INSAG-14. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

1999-01-01

The International Atomic Energy Agency's activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but they cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public's view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring the safety of nuclear power plants, the IAEA established the International Nuclear Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating, where possible, commonly shared safety principles. The present report by INSAG deals with a general approach to the safe management of the operating lifetimes of nuclear power plants. It responds to the concerns about maintaining adequate safety levels at ageing plants, even beyond their design lifetimes. Maintaining adequate safety levels implies first and foremost stringent control of equipment ageing, consistent with the design safety bases of the plants. However, as stated in the 75-INSAG-3 report, 'Basic Safety Principles for Nuclear Power Plants', nuclear safety requires a continuing quest for excellence; this implies enhancing the safety levels of operating nuclear power plants as far as reasonably practicable, with due account taken of experience and advancement in knowledge. Moreover, in view of the present situation of the nuclear industry, it may become difficult to maintain adequate competences in many countries with nuclear power programmes. These topics are considered in this latest INSAG report and released to a wider audience

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

Science.gov (United States)

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

2018-04-10

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

The safe management of sources of radiation: Principles and strategies. INSAG-11. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

1999-01-01

The IAEA activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring safety of nuclear power plants, the IAEA established the International Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating commonly shared safety principles. The present report deals with the general principles governing the safety of all sources of radiation and with application of these principles. It intends to show that, at the conceptual level, the distinction traditionally made between nuclear safety and radiation protection is hardly justifiable. It is intended primarily for those non-specialists who need to take decisions about safe management of sources of radiation and who wish to gain a better understanding of the approach followed in managing the safety of these sources

International conference on national infrastructures for radiation safety: Towards effective and sustainable systems. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

The International Atomic Energy Agency (IAEA), in co-operation with the World Health Organization (WHO), the International Labour Office (ILO), the European Commission (EC), and the OECD Nuclear Energy Agency (NEA), organized the International Conference on National Infrastructures for Radiation Safety: Towards Effective and Sustainable Systems. This book contains contributed papers submitted on pertinent issues, including stakeholder involvement, IAEA Model Projects on Upgrading Radiation Protection Infrastructure, Quality Assurance, education and training, regulatory activities, performance evaluation, source security, and emergency preparedness. The material in this book has not been edited by the IAEA. These contributed papers will be published on a CD ROM as part of the Proceedings of the Conference, along with the invited papers and discussions. The papers are grouped by topical sessions: Stakeholder Involvement in Building and Maintaining National Radiation Safety Infrastructure (National and International); Implementation Experience with The Model Projects (Views From The Countries, Positive and Negative Experiences); Resources and Services (Systematic Approach), Quality Assurance, International Support Of Services; Sustainable Education And Training: Developing Skills (National Systems And Regional Solutions); Needs for Education And Training at The International Level (Including IAEA Programmes Assisting in Establishing Adequate Infrastructures); Authorization, Inspection and Enforcement (Effectiveness and Efficiency Of The Activities Of The Regulatory Bodies), Independence of Regulatory Authorities; Performance Evaluation; Source Security and Emergency Preparedness (Infrastructure Requirements at the International, National And User's Level)

International conference on national infrastructures for radiation safety: Towards effective and sustainable systems. Contributed papers

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA), in co-operation with the World Health Organization (WHO), the International Labour Office (ILO), the European Commission (EC), and the OECD Nuclear Energy Agency (NEA), organized the International Conference on National Infrastructures for Radiation Safety: Towards Effective and Sustainable Systems. This book contains contributed papers submitted on pertinent issues, including stakeholder involvement, IAEA Model Projects on Upgrading Radiation Protection Infrastructure, Quality Assurance, education and training, regulatory activities, performance evaluation, source security, and emergency preparedness. The material in this book has not been edited by the IAEA. These contributed papers will be published on a CD ROM as part of the Proceedings of the Conference, along with the invited papers and discussions. The papers are grouped by topical sessions: Stakeholder Involvement in Building and Maintaining National Radiation Safety Infrastructure (National and International); Implementation Experience with The Model Projects (Views From The Countries, Positive and Negative Experiences); Resources and Services (Systematic Approach), Quality Assurance, International Support Of Services; Sustainable Education And Training: Developing Skills (National Systems And Regional Solutions); Needs for Education And Training at The International Level (Including IAEA Programmes Assisting in Establishing Adequate Infrastructures); Authorization, Inspection and Enforcement (Effectiveness and Efficiency Of The Activities Of The Regulatory Bodies), Independence of Regulatory Authorities; Performance Evaluation; Source Security and Emergency Preparedness (Infrastructure Requirements at the International, National And User's Level)

International surgery: definition, principles and Canadian practice

Science.gov (United States)

Lett, Ronald

2003-01-01

This article is dedicated to the Canadian international surgeon, Norman Bethune (1890–1939). International surgery is defined as a humanitarian branch of medicine concerned with the treatment of bodily injuries or disorders by incision or manipulations, emphasizing cooperation and understanding among nations and involving education, research, development and advocacy. In this article I review the colonial past, the dark ages following the Declaration of Alma-Ata, the progress made and the present challenges in international surgery. I present a definition of international surgery that recognizes the current era of surgical humanitarianism, validates a global understanding of surgical issues and promotes cooperation among nations. Included are the principles of international surgery: education, research, infrastructure development and advocacy. International surgical projects are classified according to type (clinical, relief, developmental) and integration strategy (vertical or horizontal). Also reviewed are the Canadian practice of international surgery by nongovernmental, professional and academic organizations and the requirements of international and Canadian funding agencies, the development concepts basic to all projects, including results-based management and the cross-cutting themes of gender equity, environmental protection and human safety. I recommend formalizing international surgery into a discipline as a means of promoting surgical care in low-income countries. If international surgery is to be sustained in Canada, infrastructure and support from Canadian surgeons is particularly important. An understanding of the history, definition and classification of international surgery should promote surgical care in low-income countries. PMID:14577711

Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project

International Nuclear Information System (INIS)

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-01-01

Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm/shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm/shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the ''International Handbook of Evaluated Criticality Safety Benchmark Experiments'' have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement/shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy Agency

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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)

Comparative study of Malaysian and Philippine regulatory infrastructures on radiation and nuclear safety with international standards

International Nuclear Information System (INIS)

Cayabo, Lynette B.

2013-06-01

This study presents the results of the critical reviews, analysis, and comparison of the regulatory infrastructures for radiation and nuclear safety of Malaysis and the Philippines usi ng the IAEA safety requirements, GSR Part 1, G overnment, Legal and Regulatory Framework for Safety'' as the main basis and in part, the GSR Part 3, R adiation Protection and Safety of Radiation Sources: International Basic Safety Standards . The scope of the comparison includes the elements of the relevant legislations, the regulatory system and processes including the core functions of the regulatory body (authorization, review and assessment, inspection and enforcement, development of regulations and guides); and the staffing and training of regulatory body. The respective availabe data of the Malaysian and Philippine regulatory infrastructures and current practices were gathered and analyzed. Recommendations to fill the gaps and strengthen the existing regulatory infrastructure of each country was given using as bases relevant IAEA safety guides. Based on the analysis made, the main findings are: the legislations of both countries do not contain al the elements of teh national policy and strategy for safety as well as those of teh framework for safety in GR Part I. Among the provision that need to be included in the legislations are: emergency planning and response; decommissioning of facilities safe management of radioactive wastes and spent fuel; competence for safety; and technical sevices. Provisions on coordination of different authorities with safety responsibilities within the regulatory framework for safety as well as liaison with advisory bodies and support organizations need to be enhanced. The Philippines needs to establish an independent regulatory body, ie. separate from organizations charged with promotion of nuclear technologies and responsible for facilitiesand activities. Graded approach on the system of notification and authorization by registration and

Scalable cloud without dedicated storage

Science.gov (United States)

Batkovich, D. V.; Kompaniets, M. V.; Zarochentsev, A. K.

2015-05-01

We present a prototype of a scalable computing cloud. It is intended to be deployed on the basis of a cluster without the separate dedicated storage. The dedicated storage is replaced by the distributed software storage. In addition, all cluster nodes are used both as computing nodes and as storage nodes. This solution increases utilization of the cluster resources as well as improves fault tolerance and performance of the distributed storage. Another advantage of this solution is high scalability with a relatively low initial and maintenance cost. The solution is built on the basis of the open source components like OpenStack, CEPH, etc.

International legal instruments promoting synergy's in nuclear safety, security and safeguards: myth of reality?

International Nuclear Information System (INIS)

Vasmant, A.

2009-01-01

The purpose of this article is to assess the existing synergies between nuclear safety, nuclear security and non-proliferation/safeguards resulting from the adoption of international legal instruments. Keeping in mind that a synergy is the extra success achieved by two or more elements of a system working together instead of on their own, this paper will try to evaluate the possibility of a so-called '3 S' approach to optimize the benefits so defined. to achieve this, Part 1 focuses on the history of the three regimes and their major features, while Part 2, 3 and 4 explore the various benefits of, limits to, synergies between the nuclear safety, nuclear security and safeguards regimes. Part 5 describes the potential '3 S' approach in international nuclear law. (N.C.)

Team knowledge assessment of nursing on international targets patient safety in an intensive care unit

Directory of Open Access Journals (Sweden)

Maria Nathália da Silva Souza

2017-08-01

Full Text Available Background e Objectives: The quality of hospital care provided to the patient and the safety of their stay at the site triggered discussions around the world after the analysis of epidemiological studies conducted in the USA that concluded the high rate of adverse events in the hospital setting Caused by professional error, with that the theme gained strength and motivated discussions about the care models applied to the patients. Therefore the research was aimed at evaluating the knowledge of the Nursing Team of the Intensive Care Unit sector of a public hospital in Recife-PE on the International Patient Safety Goals. Methods: A cross-sectional study with descriptive quantitative approach was carried out from June to August 2016. Data collection was performed through a semi-structured questionnaire that addressed the social and professional aspects of the respondents. The studied variables: gender, age, professional category and training time. The data were analyzed in epiinfo software version 3.2.2. Results: The sample consisted of 50 professionals, 18% of whom were Nurses and 82% were Nursing technicians. Most respondents scored more than 50% of questions about international patient safety goals and had more than one employment relationship. Conclusion: It was verified that the lack of training, work overload and more of an employment relationship can contribute to a precarious professional assistance. KEYWORDS: Patient Safety. Nursing. Safety Management. Intensive Care Units

Development of a harmonized approach to safety assessment of decommissioning: Lessons learned from international experience (DeSa project)

International Nuclear Information System (INIS)

Percival, K.; Nokhamzon, J.-G.; Ferch, R.; Batandjieva, B.

2006-01-01

The number of nuclear facilities being or planned to be shutdown as they reach the end of their design life, due to accidents or other political and social factors has been increasing worldwide. This has led to an increase in the awareness of regulators and operators of the importance of development and implementation of adequate safety requirements and criteria for decommissioning of these facilities. A general requirement at international and national levels, even for new facilities to be commissioned, is the development of a decommissioning plan, which includes evaluation of potential radiological consequences to public and workers during planned and accidental decommissioning activities. Experience has been gained in the safety assessment of decommissioning at various sites with different complexities and hazard potentials. This experience shows that various approaches have been used in conducting safety assessments and that there is a need for harmonisation of these approaches and for transferring the good practice and lessons learned to other countries, in particular developing countries with limited financial and human resources. The IAEA launched an international project on Evaluation and Demonstration of Safety during Decommissioning (DeSa) in 2004 to provide a forum for exchange of lessons learned between site operators, regulators, safety assessors and other specialists in safety assessment of decommissioning of nuclear power plants, research reactors, laboratories, nuclear fuel cycle facilities, etc. This paper presents the lessons learned through the project up to date, i.e.; (i) a common approach to safety assessment is being applied worldwide with the following steps - establishment of assessment framework; description of the facility; definition of decommissioning activities; hazard identification and analysis; calculation of consequences; and analysis of results; (ii) a deterministic approach to safety assessment is most commonly applied; (iii) a

International nuclear safety experts conclude IAEA peer review of China's regulatory system

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of senior experts on nuclear safety regulation today completed a two-week International Atomic Energy Agency (IAEA) review of the governmental and regulatory framework for nuclear safety in the People's Republic of China. The team identified good practices within the system and gave advice on areas for future improvements. The IAEA has conveyed the team's main conclusions to the Government of the People's Republic of China. The final report will be submitted to China by Autumn 2010. At the request of Chinese authorities, the IAEA assembled a team of 22 experts to conduct an Integrated Regulatory Review Service (IRRS) mission. This mission is a peer review based on the IAEA Safety Standards . It is not an inspection, nor an audit. The experts came from 15 different countries: Australia, Canada, the Czech Republic, Finland, France, Hungary, Japan, Pakistan, the Republic of Korea, Slovenia, South Africa, Sweden, the United Kingdom, Ukraine and the United States. Mike Weightman, the United Kingdom's Head of Nuclear Directorate, HSE and HM Chief Inspector of Nuclear Installations said: ''I was honoured and pleased to lead such a team of senior regulatory experts from around the world, and I was impressed by their commitment, experience and hard work to provide their best advice possible. We had very constructive interactions with the Chinese authority to maximize the beneficial impact of the mission.'' The scope of the mission included the regulation of nuclear and radiation safety of the facilities and activities regulated by the Ministry of Environmental Protection (MEP) National Nuclear Safety Administration (NNSA). The mission was conducted from 18 to 30 July, mainly in Beijing. To observe Chinese regulatory activities, the IRRS team visited several nuclear facilities, including a nuclear power plant, a manufacturer of safety components for nuclear power plants, a research reactor, a fuel cycle facility, a waste management facility

Clinical practice of image-guided spine radiosurgery - results from an international research consortium

Directory of Open Access Journals (Sweden)

Guckenberger Matthias

2011-12-01

Full Text Available Abstract Background Spinal radiosurgery is a quickly evolving technique in the radiotherapy and neurosurgical communities. However, the methods of spine radiosurgery have not been standardized. This article describes the results of a survey about the methods of spine radiosurgery at five international institutions. Methods All institutions are members of the Elekta Spine Radiosurgery Research Consortium and have a dedicated research and clinical focus on image-guided radiosurgery. The questionnaire consisted of 75 items covering all major steps of spine radiosurgery. Results Strong agreement in the methods of spine radiosurgery was observed. In particular, similarities were observed with safety and quality assurance playing an important role in the methods of all institutions, cooperation between neurosurgeons and radiation oncologists in case selection, dedicated imaging for target- and organ-at-risk delineation, application of proper safety margins for the target volume and organs-at-risk, conformal planning and precise image-guided treatment delivery, and close clinical and radiological follow-up. In contrast, three major areas of uncertainty and disagreement were identified: 1 Indications and contra-indications for spine radiosurgery; 2 treatment dose and fractionation and 3 tolerance dose of the spinal cord. Conclusions Results of this study reflect the current practice of spine radiosurgery in large academic centers. Despite close agreement was observed in many steps of spine radiosurgery, further research in form of retrospective and especially prospective studies is required to refine the details of spinal radiosurgery in terms of safety and efficacy.

A cost-effective methodology to internalize nuclear safety in nuclear reactor conceptual design

International Nuclear Information System (INIS)

Gimenez, M.; Grinblat, P.; Schlamp, M.

2003-01-01

A new methodology to perform nuclear reactor design, balancing safety and economics at the conceptual engineering stage, is presented in this work. The goal of this integral methodology is to take into account safety aspects in an optimization design process where the design variables are balanced in order to obtain a better figure of merit related with reactor economic performance. Design parameter effects on characteristic or critical safety variables, chosen from reactor behavior during accidents (safety performance indicators), are synthesized on Design Maps. These maps allow one to compare the safety indicator with limits, which are determined by design criteria or regulations, and to transfer these restrictions to the design parameters. In this way, reactor dynamic response and other safety aspects are integrated in a global optimization process, by means of additional rules to the neutronic, thermal-hydraulic, and mechanical calculations. An application of the methodology, implemented in Integrated Reactor Evaluation Program 3 (IREP3) code, to optimize safety systems of CAREM prototype is presented. It consists in balancing the designs of the Emergency Injection System (EIS), the Residual Heat Removal System (RHRS), the primary circuit water inventory and the containment height, to cope with loss of coolant and loss of heat sink (LOHS) accidental sequences, taking into account cost and reactor performance. This methodology turns out to be promising to internalize cost-efficiently safety issues. It also allows one to evaluate the incremental costs of implementing higher safety levels

National and international standards and recommendations on fire protection and fire safety assessment

International Nuclear Information System (INIS)

Berg, H.P.

2007-01-01

Experience feedback from events in nuclear facilities worldwide has shown that fire can represent a safety significant hazard. Thus, the primary objectives of fire protection programmes are to minimize both the probability of occurrence and the consequences of a fire. The regulator body expects that the licensees justify their arrangements for identifying how fires can occur and spread, assess the vulnerability of plant equipment and structures, determine how the safe operation of a plant is affected, and introduce measures to prevent a fire hazard from developing and propagating as well as to mitigate its effects in case the fire cannot be prevented. For that purpose usually a comprehensive regulatory framework for fire protection has been elaborated, based on national industrial regulations, nuclear specific regulations as well as international recommendations or requirements. Examples of such national and international standards and recommendations on fire protection and fire safety assessment as well as ongoing activities in this field are described. (orig.)

Dedicating Fermilab's Collider

Energy Technology Data Exchange (ETDEWEB)

Anon.

1986-01-15

It was a bold move to have a fullscale dedication ceremony for the new proton-antiproton Collider at the Fermilab Tevatron on 13 October, two days before the first collisions were seen. However the particles dutifully behaved as required, and over the following weekend the Collider delivered its goods at a total energy of 1600 GeV, significantly boosting the world record for laboratory collisions.

Topical points of community policy concerning nuclear safety relevant to the Internal Market

International Nuclear Information System (INIS)

Schroeder, M.

1991-01-01

Starting with the Internal Market concept, the lecture describes general and specific expectations directed to the nuclear community from a point of view of nuclear safety, and analyzes those aspects of nuclear safety, EC policy focuses on. There are the following chapters: 1. Selection of sites for nuclear installations, 2. installation and reactor safety, 3. radioactive waste management, 4. decommissioning of nuclear installations, 5. radioactive waste storage, 6. coping with nuclear accidents and other radiological emergency situations. Sophistication of public health and environmental protection within the framework of the EURATOM Treaty is seen in connection with interim and final storage as well as reprocessing of radioactive waste, and with the decommissioning of nuclear facilities on the basis of section 30 ff., and installation and reactor safety on the basis of section 203 EURATOM Treaty. Improving the protection of public health in particular is possible and necessary in order to make the EURATOM community into a proper nuclear community of law. (orig./HSCH) [de

Growth and Expansion of the International Criticality Safety Benchmark Evaluation Project and the Newly Organized International Reactor Physics Experiment Evaluation Project

Energy Technology Data Exchange (ETDEWEB)

J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

2007-05-01

Since ICNC 2003, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) has continued to expand its efforts and broaden its scope. Criticality-alarm / shielding type benchmarks and fundamental physics measurements that are relevant to criticality safety applications are not only included in the scope of the project, but benchmark data are also included in the latest version of the handbook. A considerable number of improvements have been made to the searchable database, DICE and the criticality-alarm / shielding benchmarks and fundamental physics measurements have been included in the database. There were 12 countries participating on the ICSBEP in 2003. That number has increased to 18 with recent contributions of data and/or resources from Brazil, Czech Republic, Poland, India, Canada, and China. South Africa, Germany, Argentina, and Australia have been invited to participate. Since ICNC 2003, the contents of the “International Handbook of Evaluated Criticality Safety Benchmark Experiments” have increased from 350 evaluations (28,000 pages) containing benchmark specifications for 3070 critical or subcritical configurations to 442 evaluations (over 38,000 pages) containing benchmark specifications for 3957 critical or subcritical configurations, 23 criticality-alarm-placement / shielding configurations with multiple dose points for each, and 20 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications in the 2006 Edition of the ICSBEP Handbook. Approximately 30 new evaluations and 250 additional configurations are expected to be added to the 2007 Edition of the Handbook. Since ICNC 2003, a reactor physics counterpart to the ICSBEP, The International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. Beginning in 1999, the IRPhEP was conducted as a pilot activity by the by the Organization of Economic Cooperation and Development (OECD) Nuclear Energy

Safety in paediatric imaging

International Nuclear Information System (INIS)

Carter, D.; Filice, I.; Murray, D.; Thomas, K.

2006-01-01

Those of us working in a dedicated paediatric environment are aware of the important safety issues with regard to paediatrics. Our goal when working with paediatric patients, the goal is to obtain the best quality images while keeping patients safe and their distress to a minimum. This article will discuss some of the issues regarding paediatric safety in a diagnostic imaging department, including radiation doses and the risk to paediatric patients, reducing medication errors, safe sedation practice and environmental safety. Also discussed are some conditions requiring special consideration to maintain patient safety such as epiglottitis and suspected child abuse. Promotion of a patient/family-centered care system will create an environment of trust where parents or guardians will know that their children are being well cared for in a safe, effective environment. (author)

Nuclear safety. ICFTU proposals for the international control of the nuclear energy industry

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-07-01

are strong proponents of its use and others have said that they are only prepared to accept its application if safety controls are substantially improved. All affiliates of the ICFTU are convinced that energy policy options must be widened through increased research and development of new and renewable sources and through extensive energy conservation measures. The environmental impact of all methods of energy generation must be assessed on the basis of the public availability of all relevant information. It is in this context, that whatever their views about the desirability or otherwise of nuclear power, all ICFTU affiliates recognise the immediate need to assure the highest possible level of safety for all nuclear plants and activities everywhere - for example to deal with radioactive wastes created over the last 30 years. Even if some countries opt out of nuclear power it is likely that many others will be committed to it for many years. Given the widespread effects of a catastrophic failure anywhere in the world we must therefore all be concerned to strengthen the international safety regime. Because of their historic role in campaigning for health and safety at work, unions are well placed to exercise an independent watchdog role - making use of the knowledge and skills of their members in the nuclear industry - and are also able to speak on behalf of a large membership which is representative representative of the wide public concern about nuclear safety. Immediately following the Chernobyl disaster, the ICFTU Executive Board adopted a resolution (reproduced as Appendix 2 to this document) calling for immediate steps to tighten up nuclear safety. In the light of subsequent developments, the Confederation has now given further detailed consideration to the whole question of nuclear safety and has decided to publish this report which contains detailed proposals for tighter international control of nuclear energy via the International Atomic Energy Agency (IAEA

Nuclear safety. ICFTU proposals for the international control of the nuclear energy industry

International Nuclear Information System (INIS)

1989-01-01

are strong proponents of its use and others have said that they are only prepared to accept its application if safety controls are substantially improved. All affiliates of the ICFTU are convinced that energy policy options must be widened through increased research and development of new and renewable sources and through extensive energy conservation measures. The environmental impact of all methods of energy generation must be assessed on the basis of the public availability of all relevant information. It is in this context, that whatever their views about the desirability or otherwise of nuclear power, all ICFTU affiliates recognise the immediate need to assure the highest possible level of safety for all nuclear plants and activities everywhere - for example to deal with radioactive wastes created over the last 30 years. Even if some countries opt out of nuclear power it is likely that many others will be committed to it for many years. Given the widespread effects of a catastrophic failure anywhere in the world we must therefore all be concerned to strengthen the international safety regime. Because of their historic role in campaigning for health and safety at work, unions are well placed to exercise an independent watchdog role - making use of the knowledge and skills of their members in the nuclear industry - and are also able to speak on behalf of a large membership which is representative representative of the wide public concern about nuclear safety. Immediately following the Chernobyl disaster, the ICFTU Executive Board adopted a resolution (reproduced as Appendix 2 to this document) calling for immediate steps to tighten up nuclear safety. In the light of subsequent developments, the Confederation has now given further detailed consideration to the whole question of nuclear safety and has decided to publish this report which contains detailed proposals for tighter international control of nuclear energy via the International Atomic Energy Agency (IAEA

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

Energy Secretary Dedicates ESIF at NREL | News | NREL

Science.gov (United States)

3 » Energy Secretary Dedicates ESIF at NREL Energy Secretary Dedicates ESIF at NREL September 18 prey. Enlarge image Energy Secretary Ernest Moniz (center) joins NREL Director Dan Arvizu (left) and newest Energy Department supercomputer. The high performance computer inside NREL's new Energy Systems

International cooperation for the development of consistent and stable transportation regulations to promote and enhance safety and security

International Nuclear Information System (INIS)

Strosnider, J.

2004-01-01

International commerce of radioactive materials crosses national boundaries, linking separate regulatory institutions with a common purpose and making it necessary for these institutions to work together in order to achieve common safety goals in a manner that does not place an undue burden on industry and commerce. Widespread and increasing use of radioactive materials across the world has led to increases in the transport of radioactive materials. The demand for consistency in the oversight of international transport has also increased to prevent unnecessary delays and costs associated with incongruent or redundant regulatory requirements by the various countries through which radioactive material is transported. The International Atomic Energy Agency (IAEA) is the authority for international regulation of transportation of radioactive materials responsible for promulgation of regulations and guidance for the establishment of acceptable methods of transportation for the international community. As such, the IAEA is seen as the focal point for consensus building between its Member States to develop consistency in transportation regulations and reviews and to ensure the safe and secure transport of radioactive material. International cooperation is also needed to ensure stability in our regulatory processes. Changes to transportation regulations should be based on an anticipated safety benefit supported by risk information and insights gained from continuing experience, evaluation, and research studies. If we keep safety as the principle basis for regulatory changes, regulatory stability will be enhanced. Finally, as we endeavour to maintain consistency and stability in our international regulations, we must be mindful of the new security challenges that lay before the international community as a result of a changing terrorist environment. Terrorism is a problem of global concern that also requires international cooperation and support, as we look for ways to

A Brief History of INA and ICOH SCNP: International Neurotoxicology Association and International Congress on Occupational Health Scientific Committee on Neurotoxicology and Psychophysiology

Science.gov (United States)

Two international scientific societies dedicated to research in neurotoxicology and neurobehavioral toxicology are the International Neurotoxicology Association (INA) and the International Congress on Occupational Health International Symposium on Neurobehavioral Methods and Effe...

Propofol for procedural sedation and analgesia reduced dedicated emergency nursing time while maintaining safety in a community emergency department.

Science.gov (United States)

Reynolds, Joshua C; Abraham, Michael K; Barrueto, Fermin F; Lemkin, Daniel L; Hirshon, Jon M

2013-09-01

Procedural sedation and analgesia is a core competency in emergency medicine. Propofol is replacing midazolam in many emergency departments. Barriers to performing procedural sedation include resource utilization. We hypothesized that emergency nursing time is shorter with propofol than midazolam, without increasing complications. Retrospective analysis of a procedural sedation registry for two community emergency departments with combined census of 100,000 patients/year. Demographics, procedure, and ASA physical classification status of adult patients receiving procedural sedation between 2007-2010 with midazolam or propofol were analyzed. Primary outcome was dedicated emergency nursing time. Secondary outcomes were procedural success, ED length of stay, and complication rate. Comparative statistics were performed with Mann-Whitney, Kruskal-Wallis, chi-square, or Fisher's exact test. Linear regression was performed with log-transformed procedural sedation time to define predictors. Of 328 procedural sedation and analgesia, 316 met inclusion criteria, of which 60 received midazolam and 256 propofol. Sex distribution varied between groups (midazolam 3% male; propofol 55% male; P = 0.04). Age, procedure, and ASA status were not significantly different. Propofol had shorter procedural sedation time (propofol 32.5 ± 24.2 minutes; midazolam 78.7 ± 51.5 minutes; P differences between complication rates (propofol 14%; midazolam 13%; P = 0.88) or emergency department length of stay (propofol 262.5 ± 132.8 minutes; midazolam 288.6 ± 130.6 minutes; P = 0.09). Use of propofol resulted in shorter emergency nursing time and higher procedural success rate than midazolam with a comparable safety profile. Copyright © 2013 Emergency Nurses Association. Published by Mosby, Inc. All rights reserved.

Approaches to safety, environment and regulatory approval for the International Thermonuclear Experimental Reactor

International Nuclear Information System (INIS)

Saji, G.; Bartels, H.W.; Chuyanov, V.; Holland, D.; Kashirski, A.V.; Morozov, S.I.; Piet, S.J.; Poucet, A.; Raeder, J.; Rebut, P.H.; Topilski, L.N.

1995-01-01

International Thermonuclear Experimental Reactor (ITER) Engineering Design Activities (EDA) in safety and environment are approaching the point where conceptual safety design, topic studies and research will give way to project oriented engineering design activities. The Joint Central Team (JCT) is promoting safety design and analysis necessary for siting and regulatory approval. Scoping studies are underway at the general level, in terms of laying out the safety and environmental design framework for ITER. ITER must follow the nuclear regulations of the host country as the future construction site of ITER. That is, regulatory approval is required before construction of ITER. Thus, during the EDA, some preparations are necessary for the future application for regulatory approval. Notwithstanding the future host country's jurisdictional framework of nuclear regulations, the primary responsibility for safety and reliability of ITER rests with the legally responsible body which will operate ITER. Since scientific utilization of ITER and protection of the large investment depends on safe and reliable operation of ITER, we are highly motivated to achieve maximum levels of operability, maintainability, and safety. ITER will be the first fusion facility in which overall 'nuclear safety' provisions need to be integrated into the facility. For example, it will be the first fusion facility with significant decay heat and structural radiational damage. Since ITER is an experimental facility, it is also important that necessary experiments can be performed within some safety design limits without requiring extensive regulatory procedures. ITER will be designed with such a robust safety envelope compatible with the fusion power and the energy inventories. The basic approach to safety will be realized by 'defense-in-depth'. (orig.)

Dedicated auxiliary power units for Hybrid Electric Vehicles

NARCIS (Netherlands)

Mourad, S.; Weijer, C.J.T. van de

1998-01-01

The use of a dedicated auxiliary power unit is essential to utilize the potential that hybrid vehicles offer for efficient and ultra-clean transportation. An example of a hybrid project at the TNO Road-Vehicles Research Institute shows the development and the results of a dedicated auxiliary power

Opening remarks at the International Conference on the Safety and Security of Radioactive Sources, Bordeaux, France, 27 June 2005

International Nuclear Information System (INIS)

Taniguchi, T.

2005-01-01

The vast majority of radioactive sources are controlled properly. However, radiological accidents have occurred in all regions of the world - which indicates that there is not always sufficient control of sources throughout their life cycle. Even advanced countries with developed regulatory systems lose track of sources each year resulting in orphan sources with the potential to cause incidents or accidents. Actually, an increasing number of cases of uncontrolled movement of sources are reported the Agency's Illicit Trafficking Database (ITDB). The International Conference on Security of Radioactive Sources, held in Vienna, Austria, in 2003, addressed these concerns and called for international initiatives, including the updating of the IAEA Action Plan for the Safety and Security of Radioactive Sources. As a direct result of the updated Action Plan the Code of Conduct on the Safety and Security of Radioactive Sources was revised and approved by the Board of Governors in 2003, its supporting Guidance on the Import and Export of Radioactive Sources was developed and approved in 2004 and the Safety Guide on Categorization of Radioactive Sources was completed recently. All three documents were developed under the auspices of the IAEA to achieve international consensus and they play a central role in this Conference. It is worth noting that more than 70 countries have already expressed their intention to follow the guidance given in the Code of Conduct on the Safety and Security of Radioactive Sources - and I would like to encourage more countries to do so. The Agency has been promoting for some time now the idea of a Global Nuclear Safety Regime. At the heart of this regime is a strong and effective national safety infrastructure where - as an overriding priority - safety issues are given the attention warranted by their significance. The need for sustainable regulatory infrastructure for the safety and security of radioactive sources was discussed at the

International R&M/Safety Cooperation Lessons Learned Between NASA and JAXA

Science.gov (United States)

Fernandez, Rene; Havenhill, Maria T.; Zampino, Edward J.; Kiefer, Dwayne E.

2013-01-01

Presented are a number of important experiences gained and lessons learned from the collaboration of the National Aeronautics and Space Administration (NASA) and the Japanese Aerospace Exploration Agency (JAXA) on the CoNNeCT (Communications, Navigation, and Networking re-Configurable Testbed) project. Both space agencies worked on the CoNNeCT Project to design, assemble, test, integrate, and launch a communications testbed facility mounted onto the International Space Station (ISS) truss. At the 2012 RAMS, two papers about CoNNeCT were presented: one on Ground Support Equipment Reliability & System Safety, and the other one on combined application of System Safety & Reliability for the flight system. In addition to the logistics challenges present when two organizations are on the opposite side of the world, there is also a language barrier. The language barrier encompasses not only the different alphabet, it encompasses the social interactions; these were addressed by techniques presented in the paper. The differences in interpretation and application of Spaceflight Requirements will be discussed in this paper. Although many, but definitely not all, of JAXA's Spaceflight Requirements were inspired by NASA, there were significant and critically important differences in how they were interpreted and applied. This paper intends to summarize which practices worked and which did not for an international collaborative effort so that future missions may benefit from our experiences. The CoNNeCT flight system has been successfully assembled, integrated, tested, shipped, launched and installed on the ISS without incident. This demonstrates that the steps taken to facilitate international understanding, communication, and coordination were successful and warrant discussion as lessons learned.

Block 4 and Cluster D - Safety

CERN Multimedia

CERN. Geneva

2016-01-01

After transfer of Bloc4 test facility to SM18 its safety system was upgraded in 2014/2015 for its 3 existing test cryostats. In 2016 a new test facility HFM (High Field Magnet) was integrated in the Bloc4. A new test facility Cluster D which is similar to HFM is in a process of installation in SM18. The Presentation is dedicated to safety strategy of Bloc4 and Cluster D and focused on an analysis of risk conditions and on the real behaviour of safety valves in case of discharge. Protection of sub-atmospheric circuits is also discussed.

R&D Challenges for SFR Design and Safety Analysis – Opportunities for International Cooperations

International Nuclear Information System (INIS)

Devictor, Nicolas

2013-01-01

Examples of R&D challenges related to safety have been presented. For any domain, R&D activities includes modelling, codes development and their V&V process, with the support of experimental programs. The success in the R&D will help the safety case and the acceptability of SFR. Some of these activities are relevant for international cooperation especially benchmarks and sharing of experimental facilities. This last point could take benefit of recent catalogues experimental facilities (already operational or in project), for example from the TAREF Task Force of OECD/NEA and the European project ADRIANA

The safe management of sources of radiation: Principles and strategies. INSAG-11. A report by the International Nuclear Safety Advisory Group (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

The IAEA activities relating to nuclear safety are based upon a number of premises. First and foremost, each Member State bears full responsibility for the safety of its nuclear facilities. States can be advised, but cannot be relieved of this responsibility. Secondly, much can be gained by exchanging experience; lessons learned can prevent accidents. Finally, the image of nuclear safety is international; a serious accident anywhere affects the public view of nuclear power everywhere. With the intention of strengthening its contribution to ensuring safety of nuclear power plants, the IAEA established the International Safety Advisory Group (INSAG), whose duties include serving as a forum for the exchange of information on nuclear safety issues of international significance and formulating commonly shared safety principles. The present report deals with the general principles governing the safety of all sources of radiation and with application of these principles. It intends to show that, at the conceptual level, the distinction traditionally made between nuclear safety and radiation protection is hardly justifiable. It is intended primarily for those non-specialists who need to take decisions about safe management of sources of radiation and who wish to gain a better understanding of the approach followed in managing the safety of these sources

New set of Chemical Safety rules

CERN Multimedia

HSE Unit

2011-01-01

A new set of four Safety Rules was issued on 28 March 2011: Safety Regulation SR-C ver. 2, Chemical Agents (en); General Safety Instruction GSI-C1, Prevention and Protection Measures (en); General Safety Instruction GSI-C2, Explosive Atmospheres (en); General Safety Instruction GSI-C3, Monitoring of Exposure to Hazardous Chemical Agents in Workplace Atmospheres (en). These documents form part of the CERN Safety Rules and are issued in application of the “Staff Rules and Regulations” and of document SAPOCO 42. These documents set out the minimum requirements for the protection of persons from risks to their occupational safety and health arising, or likely to arise, from the effects of hazardous chemical agents that are present in the workplace or used in any CERN activity. Simultaneously, the HSE Unit has published seven Safety Guidelines and six Safety Forms. These documents are available from the dedicated Web page “Chemical, Cryogenic and Biological Safety&...

76 FR 58049 - Atomic Safety and Licensing Board; Honeywell International, Inc.; Metropolis Works Uranium...

Science.gov (United States)

2011-09-19

... NUCLEAR REGULATORY COMMISSION [Docket No. 40-3392-MLA; ASLBP No. 11-910-01-MLA-BD01] Atomic Safety and Licensing Board; Honeywell International, Inc.; Metropolis Works Uranium Conversion Facility... assurance for its Metropolis Works uranium conversion facility in Metropolis, Illinois. \\1\\ LBP-11-19, 74...

The Making of discussion groups in a combined process of internal evaluation of safety culture

International Nuclear Information System (INIS)

German, S.; Buedo, J. L.; La Salabarnada, E.; Navajas, J.; Silla, I.

2012-01-01

The purpose of this paper is to show the design and evaluation of safety culture conducted in the Cofrentes nuclear plant. The process has combined the use of different methodologies and techniques and has allowed the participation of different internal and external stake holders. For internal assessment discussion groups were conducted. These groups, which were designed and analyzed by the CIEMAT, were led by employees from different levels of Cofrentes.

Applying the WHO conceptual framework for the International Classification for Patient Safety to a surgical population.

Science.gov (United States)

McElroy, L M; Woods, D M; Yanes, A F; Skaro, A I; Daud, A; Curtis, T; Wymore, E; Holl, J L; Abecassis, M M; Ladner, D P

2016-04-01

Efforts to improve patient safety are challenged by the lack of universally agreed upon terms. The International Classification for Patient Safety (ICPS) was developed by the World Health Organization for this purpose. This study aimed to test the applicability of the ICPS to a surgical population. A web-based safety debriefing was sent to clinicians involved in surgical care of abdominal organ transplant patients. A multidisciplinary team of patient safety experts, surgeons and researchers used the data to develop a system of classification based on the ICPS. Disagreements were reconciled via consensus, and a codebook was developed for future use by researchers. A total of 320 debriefing responses were used for the initial review and codebook development. In total, the 320 debriefing responses contained 227 patient safety incidents (range: 0-7 per debriefing) and 156 contributing factors/hazards (0-5 per response). The most common severity classification was 'reportable circumstance,' followed by 'near miss.' The most common incident types were 'resources/organizational management,' followed by 'medical device/equipment.' Several aspects of surgical care were encompassed by more than one classification, including operating room scheduling, delays in care, trainee-related incidents, interruptions and handoffs. This study demonstrates that a framework for patient safety can be applied to facilitate the organization and analysis of surgical safety data. Several unique aspects of surgical care require consideration, and by using a standardized framework for describing concepts, research findings can be compared and disseminated across surgical specialties. The codebook is intended for use as a framework for other specialties and institutions. © The Author 2016. Published by Oxford University Press in association with the International Society for Quality in Health Care; all rights reserved.

Global Food Safety-International Consumers' Rights?

Science.gov (United States)

Hussain, Malik Altaf

2013-10-11

Your submissions to this Special Issue "Food Microbiology and Safety" of Foods -a new open access journal-are welcome. We understand there are no foodborne illness-free zones in the world. Therefore, a proper understanding of foodborne pathogens and the factors that impact their growth, survival and pathogenesis would equip us with tools to ensure global food safety. This Special Issue publishes articles on different aspects of food microbiology and safety. [...].

Analysis of Critical Characteristics for Safety Graded Personnel Computers in the KNICS Architecture

International Nuclear Information System (INIS)

Lee, Hyun Chul; Lee, Dong Young

2009-01-01

Critical characteristics analysis of a safety related item is to identify characteristics to be verified to replace an original item with the dedicated item. It is sure that the dedicated item meeting critical characteristics would perform its intended safety function instead of the specified item. KNICS project developed two safety systems: IDiPS RPS (Reactor Protection System) and IDiPS ESF-CCS (Engineered Safety Features-Component Control System). Two safety systems of IDiPS are equipped with personnel computers, so-called COMs (Cabinet Operator Modules), in their cabinets. The personnel computers, COMs, are responsible for safety system monitoring, testing, and maintaining. Even though two safety systems are safety critical system, the personnel computers of two systems, i.e. COMs, are not graded as safety-graded items. Regulation requirements are expected to be strengthened, and the functions of the personnel computer may be enhanced to include safety-related functions and safety functions, it would be necessary that the grade of the personnel computers is adjusted to a higher level, the safety grade. To try to upgrade a non safety system, i.e. COMs, to a safety system, its safety functions and requirements, i.e. critical characteristics, must be identified and verified. This paper describes the process of the identification of critical characteristics and the results of analysis

SMiRT 23. 14{sup th} international seminar on fire safety in nuclear power plants and installations

Energy Technology Data Exchange (ETDEWEB)

Roewekamp, Marina (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany); Berg, Heinz-Peter [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

2015-12-15

In the frame of the project 3614R01575 funded by the German Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (Bundesministerium fuer Umwelt, Naturschutz, Bau und Reaktorsicherheit, BMUB) the meanwhile fourteenth international seminar on ''Fire Safety in Nuclear Power Plants and Installations'' has been conducted as P ost-Conference Seminar of the 23{sup rd} International Conference on Structural Mechanics In Reactor Technology (SMiRT 23) in Salford, United Kingdom in August 2015. The following seminar proceedings contain the entire twenty-one technical contributions to the two day s seminar with in total fifty-five participants from ten countries in Asia, Europe and America.

Safety case: An international perspective

International Nuclear Information System (INIS)

Pescatore, C.; Voinis, S.

2002-01-01

In recent years, it has become more and more evident that repository development will involve a number of stages punctuated by interdependent decisions on whether and how to move to the next stage. These decisions require a clear and traceable presentation of technical arguments that will help in giving confidence in the feasibility and safety of the proposed concept. The depth of understanding and technical information available to support decisions will vary from step to step. A safety case is a key item to support the decision to move to the next stage in repository development. Progress is noted, in the past decade, in the performance and safety assessment areas, particularly in the methodologies for repository system analysis. Progress is also observed regarding the understanding of the natural system and its characterisation, treatment of uncertainties, and modelling. Some areas are under active development, e.g. the area of scenario development and analysis. Finally, to increase confidence, rigorous quality assurance procedures need to be implemented, as well as the factoring of the contribution of R and D in underground research laboratories. The paper summarises the lessons learnt within relevant NEA initiatives as they evolved over the course of a decade and now allow a comprehensive view of what constitutes a safety case. (author)

Report by the ASN on the situation of nuclear safety and radiation protection in France in 2013

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Delmestre, Alain; Bardet, Marie-Christine; Covard, Fabienne; Javay, Olivier

2014-01-01

In its first chapters, this huge report presents the various actions undertaken by the ASN. It proposes a detailed overview of the issue of ionizing radiations and risks for health and for the environment in the field of nuclear activities, presents and comments the principles and actors of the control of nuclear safety and of radiation protection, presents the different elements of the legal framework, describes and comments the control of nuclear activities and of exposures to ionizing radiations. The next chapters address the actions controlled by the ASN: radiological and post-accidental radiological situations, present measures related to public information and transparency, overview of international relationships, regional overview of nuclear safety and radiation protection, medical use of ionizing radiations, industrial, research and veterinary uses and the issue of source safety, the issue of radioactive material transportation. Issues of nuclear safety and radiation protection are then discussed for electronuclear plants, for installations dedicated to the nuclear fuel cycle, for various research and industrial nuclear installations, for the dismantling of base nuclear installations, and for radioactive wastes and polluted sites and soils

Key asset - inherent safety of LMFBR Pool Plant

International Nuclear Information System (INIS)

Marchaterre, J.F.; Sevy, R.H.; Lancet, R.T.; Mills, J.C.

1984-04-01

The safety approach used in the design of the Large Pool Plant emphasizes use of the intrinsic characteristics of Liquid Metal Fast Breeder Reactors to incorporate a high degree of safety in the design and reduce cost by providing simpler (more reliable) dedicated safety systems. Correspondingly, a goal was not to require the action of active systems to prevent significant core damage and/or provide large grace periods for all anticipated transients. The key safety features of the plant are presented and the analysis of representative flow and power transients are presented to show that the design goal has been satisfied

Key asset--Inherent safety of LFMBR pool plant

International Nuclear Information System (INIS)

Marchaterre, J.F.; Lancet, R.T.; Mills, J.C.; Sevy, R.H.

1984-01-01

The safety approach used in the design of the Large Pool Plant emphasizes use of the intrinsic characteristics of Liquid Metal Fast Breeder Reactors to incorporate a high degree of safety in the design and reduce cost by providing simpler (more reliable) dedicated safety systems. Correspondingly, a goal was not to require the action of active systems to prevent significant core damage and/or provide large grace periods for all anticipated transients. The key safety features of the plant are presented and the analysis of representative flow and power transients are presented to show that the design goal has been satisfied

Development of the international status of science and technology concerning methods and tools for operational and long-term safety cases

International Nuclear Information System (INIS)

Seher, Holger; Beuth, Thomas; Bracke, Guido; Kock, Ingo; Mayer, Kim-Marisa; Moog, Helge C.; Uhlmann, Stephan; Weyand, Torben

2016-09-01

The project ''development of the international status of science and technology concerning methods and tools for operational and long-term safety cases'' covers the following key aspects: global aspects of the methodology for scenario assumption for the operational phase following closure, potential analysis of the derives safety cases for the project Gorleben, determination of the solid phase composition of high-level radioactive wastes using geochemical modeling calculations, search for an adequate approach for the calculation of density and viscosity of saline solutions for the future use in GRS computer codes, international approaches for an integral analysis for the host rocks clay and granite in relation to the safety requirements of BMUB.

Usage of Commercial Grade Programmable Digital Systems in Safety Related Applications

International Nuclear Information System (INIS)

Mandic, D.

2006-01-01

This paper explains methods and conditions, which if completely and correctly fulfilled, enable an operating NPP (Nuclear Power Plant) licensed and operating in accordance with the US codes and US regulatory requirements to use a commercial grade programmable digital device (PLC - Programmable Digital Controller, digital controller, digital computer or process computer) in a safety related application in a NPP. In mid 80's, when an intensive construction cycle of the new NPPs in the U.S.A. was completed, many equipment manufacturers either disappeared from the market or they abandoned their product lines that were designed and manufactured under 10 CFR Part 50 Appendix B quality assurance program. The quality assurance as defined by 10 CFR Part 50 Appendix B comprises all those planned and systematic actions necessary to provide adequate confidence that a Structure, System or Component (SSC) will perform satisfactorily in service . The operating NPPs faced the problem related to the availability of qualified equipment, components and spare parts. The US NRC (Nuclear Regulatory Commission) recognized that problem timely (Oct. 1978 revision of 10CFR21) and required a commercial grade item to be dedicated before it could be used as a basic component. A special process named Dedication of CGI - Commercial Grade Items if conducted properly, provides reasonable assurance that a commercial grade item to be used as a basic component will perform its intended safety related function and, in this respect, is deemed equivalent to an item designed and manufactured under 10 CFR Part 50 Appendix B. After that, the Dedication of CGI has been widely used mostly for relatively simple mechanical, electrical, and IandC components and spare parts. In order to provide guidance to the dedication process, EPRI has issued two documents (EPRI NP-5652 and Supplemental Guidance for EPRI NP-5652). All nuclear power plants, which comply with the US nuclear regulatory requirements, hindered as

10 CFR 70.62 - Safety program and integrated safety analysis.

Science.gov (United States)

2010-01-01

...; (iv) Potential accident sequences caused by process deviations or other events internal to the... have experience in nuclear criticality safety, radiation safety, fire safety, and chemical process... this safety program; namely, process safety information, integrated safety analysis, and management...

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

Following the Fukushima Daiichi Nuclear Power Plant accident in March 2011, considerable public concern arose regarding the management of food in and from Japan. These concerns were raised in Japan, as well as in surrounding countries. Unfortunately, it was quickly realised that the existing frameworks for decision-making with regard to food safety seemed inadequate for addressing the challenges presented by this unprecedented event. The areas affected by the accident are heavily agricultural, producing many food products, including rice, vegetables, beef, persimmons and peaches. In addition, the area is an important region for fisheries in Japan. The food products of the region had been very well-regarded both in Japan and abroad. However, some of the people living in affected areas remain concerned for their health and for their future livelihood. In the aftermath of the accident, populations living outside the directly affected areas were also concerned about consuming food products from Fukushima. In Tokyo, which is located approximately 240 km south of Fukushima, some shops ceased entirely to carry certain food items, simply because the best examples were commonly from the Fukushima region. Many of Japan's trading partners, which were concerned about importing food thought to be contaminated, showed similar reactions. These concerns posed a complex, multi-layered problem with local, national and international implications, for which there were no broad, internationally-agreed approaches. This stands as an important lesson to be absorbed from the accident and highlights a need for international focus. To secure distribution of safe agricultural and livestock products, good agricultural practices to produce safe food and feed, including reduction measures of radionuclides from farmland, have been implemented in Japan. The regulation limits have been set consistent with the approach stipulated in the international standards/guidelines, i.e. Codex guidelines. Food

Total safety management: An approach to improving safety culture

International Nuclear Information System (INIS)

Blush, S.M.

1993-01-01

A little over 4 yr ago, Admiral James D. Watkins became Secretary of Energy. President Bush, who had appointed him, informed Watkins that his principal task would be to clean up the nuclear weapons complex and put the US Department of Energy (DOE) back in the business of producing tritium for the nation's nuclear deterrent. Watkins recognized that in order to achieve these objectives, he would have to substantially improve the DOE's safety culture. Safety culture is a relatively new term. The International Atomic Energy Agency (IAEA) used it in a 1986 report on the root causes of the Chernobyl nuclear accident. In 1990, the IAEA's International Nuclear Safety Advisory Group issued a document focusing directly on safety culture. It provides guidelines to the international nuclear community for measuring the effectiveness of safety culture in nuclear organizations. Safety culture has two principal aspects: an organizational framework conducive to safety and the necessary organizational and individual attitudes that promote safety. These obviously go hand in hand. An organization must create the right framework to foster the right attitudes, but individuals must have the right attitudes to create the organizational framework that will support a good safety culture. The difficulty in developing such a synergistic relationship suggests that achieving and sustaining a strong safety culture is not easy, particularly in an organization whose safety culture is in serious disrepair

International Safety Management – Safety Management Systems and the Challenges of Changing a Culture

Directory of Open Access Journals (Sweden)

Gregory Hanchrow

2017-03-01

Full Text Available Over the past generation, the ISM code has brought forth tremendous opportunities to investigate and enhance the human factor in shipping through the implementation of Safety Management Systems. One of the critical factors to this implementation has been mandatory compliance and a requirement for obtaining a Document of Compliance (DOC for vessels operating globally or at least internationally. A primary objective of these systems is to maintain them as “living” or “dynamic” systems that are always evolving. As the ISM code has evolved, there have been instances where large organizations have opted to maintain a voluntary DOC from their respective class society. This has been accomplished with a large human factor element as typically an organizational culture does not always accept change readily especially if there is not a legal requirement to do so. In other words, when considering maritime training is it possible that organizations may represent cultural challenges? The intent of this paper will be to research large maritime operations that have opted for a document of compliance voluntarily and compare them to similar organizations that have been mandated by international law to do the same. The result should be to gain insight into the human factors that must contribute to a culture change in the organization for the purposes of a legal requirement versus the human factors that contribute to a voluntary establishment of a safety management system. This analysis will include both the executive decision making that designs a system implementation and the operational sector that must execute its implementation. All success and failures of education and training can be determined by the outcome. Did the training achieve its goal? Or has the education prepared the students to embrace a new idea in conjunction with a company goal or a new regulatory scheme? In qualifying the goal of a successful ISM integration by examining both

Development, Dedication and Application of an Automatic Seismic Trip System for Nuclear Power Plants of Taiwan Power Company

International Nuclear Information System (INIS)

Liao, Hsin-kai; Lee, Chung-lin; Chen, Chang-kuo; Hsu, Yao-tung; Shyu, Shian-shing

2011-01-01

This paper describes the setups of Automatic Seismic Trip System (ASTS), including development, dedication and implementation, for Nuclear Power Plants (NPPs) of Taiwan Power Company (TPC). The purposed ASTS was designed to trip the reactor when big earthquake occurs. These ASTS were classified as class 1E equipment. They were developed and dedicated for safety applications in accordance with IEEE 323-1983, IEEE 344-1987, IEEE 383-1974 and Reg. Guide 1.180 R1. In order to meet the technical specification required by TPC, three sub-units in the ASTS were developed: Earthquake sensors: Kinemetrices FBA-23 triaxial accelerometers are selected since they were successfully used in Taiwan for seismic monitoring for more than 10 years. Signal conditioning module: It is designed to reduce noise from motion accelerometer (FBA-23) and then transmit seismic signal to the set-point and trip unit via instrument amplify circuit, 0.1 to 10Hz band pass filter circuit, absolute-value converter and voltage to current converter. Trip control module: after comparing the seismic signal level and set-point, the result will decide whether to drive the output relay or not. The output relay is used as the interface between ASTS and the reactor protection system in NPP. For the commercial grade item dedication for safety application, five processes were conducted. Those processes are Seismic test: to use plant specific required response spectrum (RRS), the test required spectrum should envelop RRS: Seismic auto-trip accuracy test: must not trip when filtered PA below set point minus 0.05g, and must trip when filtered PA exceeds set point over 0.05g. Trip signals occurred within 10 second interval are considered as same events: NEMA4 water proof test for sensor box: Anti-radiation test: 8.76x100 rads over 40 years: EMI/EMC test: follow RG 1.180 requirement. The ASTS were installed in three NPPs, six units in total, without connection to RPS in 2006. After one year reliable operation, the

Neutron dynamics of fast-spectrum dedicated cores for waste transmutation

International Nuclear Information System (INIS)

Massara, S.

2002-04-01

Among different scenarios achieving minor actinide transmutation, the possibility of double strata scenarios with critical, fast spectrum, dedicated cores must be checked and quantified. In these cores, the waste fraction has to be at the highest level compatible with safety requirements during normal operation and transient conditions. As reactivity coefficients are poor in such critical cores (low delayed neutron fraction and Doppler feed-back, high coolant void coefficient), their dynamic behaviour during transient conditions must be carefully analysed. Three nitride-fuel configurations have been analysed: two liquid metal-cooled (sodium and lead) and a particle-fuel helium-cooled one. A dynamic code, MAT4 DYN, has been developed during the PhD thesis, allowing the study of loss of flow, reactivity insertion and loss of coolant accidents, and taking into account two fuel geometries (cylindrical and spherical) and two thermal-hydraulics models for the coolant (incompressible for liquid metals and compressible for helium). Dynamics calculations have shown that if the fuel nature is appropriately chosen (letting a sufficient margin during transients), this can counterbalance the bad state of reactivity coefficients for liquid metal-cooled cores, thus proving the interest of this kind of concept. On the other side, the gas-cooled core dynamics is very badly affected by the high value of the helium void coefficient (which is a consequence of the choice of a hard spectrum), this effect being amplified by the very low thermal inertia of particle-fuel design. So, a new kind of concept should be considered for a helium-cooled fast-spectrum dedicated core. (authors)

Survey VS audit by using method 2 to dedicate commercial grade services

International Nuclear Information System (INIS)

Martinez ayucar, F. J.

2014-01-01

Since the start of the commercial grade dedications, both 10CFR21 and EPRI documents, plus the dedication of commercial grade components, and the stage of commercial grade dedication of the services contemplated. And recently the NRC through various communications and answers trafficking among other issues the commercial grade dedication service. The NRC has detected repeatedly incorrect application of the survey as a method of commercial grade dedication and instead has done an audit of the program elements of commercial quality. (Author)

Nuclear power safety

International Nuclear Information System (INIS)

1991-11-01

This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

Sources of Safety Data and Statistical Strategies for Design and Analysis: Transforming Data Into Evidence.

Science.gov (United States)

Ma, Haijun; Russek-Cohen, Estelle; Izem, Rima; Marchenko, Olga V; Jiang, Qi

2018-03-01

Safety evaluation is a key aspect of medical product development. It is a continual and iterative process requiring thorough thinking, and dedicated time and resources. In this article, we discuss how safety data are transformed into evidence to establish and refine the safety profile of a medical product, and how the focus of safety evaluation, data sources, and statistical methods change throughout a medical product's life cycle. Some challenges and statistical strategies for medical product safety evaluation are discussed. Examples of safety issues identified in different periods, that is, premarketing and postmarketing, are discussed to illustrate how different sources are used in the safety signal identification and the iterative process of safety assessment. The examples highlighted range from commonly used pediatric vaccine given to healthy children to medical products primarily used to treat a medical condition in adults. These case studies illustrate that different products may require different approaches, and once a signal is discovered, it could impact future safety assessments. Many challenges still remain in this area despite advances in methodologies, infrastructure, public awareness, international harmonization, and regulatory enforcement. Innovations in safety assessment methodologies are pressing in order to make the medical product development process more efficient and effective, and the assessment of medical product marketing approval more streamlined and structured. Health care payers, providers, and patients may have different perspectives when weighing in on clinical, financial and personal needs when therapies are being evaluated.

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

International Nuclear Information System (INIS)

2009-01-01

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

The AMFEC: a tool for dedications

International Nuclear Information System (INIS)

Pastor Escobar, H.; Gomar Vidal, J.

2014-01-01

The process of dedication, consists of a series of activities intended to ensure that a component of commercial grade can be used in applications related with the Security at nuclear facilities. However, in one of the steps of essential dedication, is often the problem defined with certain accuracy the most relevant characteristics or critical acceptance of the component characteristics, which through its verification, give by valid the commercial component for security-related use. Due to lack of information, they can sometimes not be identified clearly, and therefore it is necessary to resort to some alternative method that will allow us to define them, the AMFEC (analysis of failure modes, effects and criticality. (Author)

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2001-01-01

verification' are used differently in different countries. The way that these terms have been used in this Safety Guide is explained in Section 2. The term 'design' as used here includes the specifications for the safe operation and management of the plant. This Safety Guide identifies the key recommendations for carrying out the safety assessment and the independent verification. It provides detailed guidance in support of IAEA, Safety of Nuclear Power Plants: Design, Safety Standards Series No. NS-R-1 (2000), particularly in the area of safety analysis. However, this does not include all the technical details which are available and reference is made to other IAEA publications on specific design issues and safety analysis methods. Specific deterministic or probabilistic safety targets or radiological limits can vary in different countries and are the responsibility of the regulatory body. This Safety Guide provides some references to targets and limits established by international organizations. Operators, and sometimes designers, may also set their own safety targets which may be more stringent than those set by the regulator or may address different aspects of safety. In some countries operators are expected to do this as part of their 'ownership' of the entire safety case. This Safety Guide does not include specific recommendations for the safety assessment of those plant systems for which dedicated Safety Guides exist. Section 2 defines the terms 'safety assessment', 'safety analysis' and 'independent verification' and outlines their relationship. Section 3 gives the key recommendations for the safety assessment of the principal and plant design requirements. Section 4 gives the key recommendations for safety analysis. It describes the identification of postulated initiating events (PIEs), which are used throughout the safety assessment including the safety analysis, the deterministic transient analysis and severe accident analysis, and the probabilistic safety analysis

International nuclear safety experts conclude IAEA peer review of Canada's regulatory system

International Nuclear Information System (INIS)

2009-01-01

Full text: An international team of nuclear safety experts today completed a two-week IAEA review of the regulatory framework and effectiveness of the Canadian Nuclear Safety Commission (CNSC). The team identified good practices within the system and gave advice on some areas for improvement. The IAEA has conveyed initial findings to Canadian authorities; the final report will be submitted by autumn. The International Atomic Energy Agency (IAEA) assembled a team of nuclear, radiation, and waste safety experts at the request of the Government of Canada, to conduct an Integrated Regulatory Review Service (IRRS) mission. The mission from 31 May to 12 June was a peer review based on IAEA Standards, not an inspection, nor an audit. The scope of the mission included sources, facilities and activities regulated by the CNSC: the operation of nuclear power plants (NPPs), research reactors and fuel cycle facilities; the refurbishment or licensing of new NPPs; uranium mining; radiation protection and environmental protection programmes; and the implementation of IAEA Code of Conduct on Safety and Security of Radioactive Sources. The 21-member team from 13 IAEA States and from the IAEA itself reviewed CNSC's work in all relevant areas: legislative and governmental responsibilities; responsibilities and functions; organization; activities of the regulatory body, including the authorization process, review and assessment, inspection and enforcement, the development of regulations, as well as guides and its the management system of CNSC. The basis for the review was a well-prepared self-assessment by the CNSC, including an evolution of its strengths and proposed actions to improve its regulatory effectiveness. Mr. Shojiro Matsuura, IRRS Team Leader and President of the Japanese Nuclear Safety Research Association, said the team 'was impressed by the extensive preparation at all CNSC staff levels.' 'We identified a number of good practices and made recommendations and suggestions

International conference on challenges faced by technical and scientific support organizations in enhancing nuclear safety. Contributed papers and presentations

International Nuclear Information System (INIS)

2007-01-01

Over the past two decades, the IAEA has conducted a series of major conferences that have addressed topical issues and strategies critical to nuclear safety for consideration by the world's nuclear regulators. More recently, the IAEA organized the International Conference on Effective Nuclear Regulatory Systems - Facing Safety and Security Challenges, held in Moscow in 2006. The Moscow conference was the first of its kind, because it brought together senior regulators of nuclear safety, radiation safety and security from around the world to discuss how to improve regulatory effectiveness with the objective of improving the protection of the public and the users of nuclear and radioactive material. The International Conference on Challenges Faced by Technical and Scientific Support Organizations in Enhancing Nuclear Safety was held in Aix-en-Provence, France, from 23 to 27 April 2007. This conference, again, was the first of its kind, because it was the first to address technical and scientific support organizations (TSOs), the role they play in supporting either the national regulatory bodies or the industry in making optimum safety decisions and the challenges they face in providing this support. This conference provided a forum for the TSOs to discuss these and other issues with the organizations to which they provide this support - that is, the regulators and the operators/industry - as well as with other stakeholders such as research organizations and public authorities. This conference can also be considered to have a link to the Moscow conference. The Moscow conference concluded that effective regulation of nuclear safety is vital for the safe use of nuclear energy and associated technologies, both now and in the future, and is an essential prerequisite for establishing an effective Global Nuclear Safety Regime. The Moscow conference also highlighted the importance of continued and improved international cooperation in the area of nuclear safety. These

Global nuclear safety culture

International Nuclear Information System (INIS)

1997-01-01

As stated in the Nuclear Safety Review 1996, three components characterize the global nuclear safety culture infrastructure: (i) legally binding international agreements; (ii) non-binding common safety standards; and (iii) the application of safety standards. The IAEA has continued to foster the global nuclear safety culture by supporting intergovernmental collaborative efforts; it has facilitated extensive information exchange, promoted the drafting of international legal agreements and the development of common safety standards, and provided for the application of safety standards by organizing a wide variety of expert services

Papers submitted to the international forum ''one decade after Chernobyl: nuclear safety aspects''. Working material

International Nuclear Information System (INIS)

1996-01-01

The objective of the forum is to review the remedial measures taken since the Chernobyl accident for improving the safety of RBMK reactors and the Chernobyl containment structure (sarcophagus). The forum will also serve to exchange information on national, bilateral and multilateral efforts for the enhancement of RBMK safety. The conclusions and recommendations will serve as a basis for a background paper to be prepared for presentation, by the forum chairman, at the International Conference ''One decade after Chernobyl'' to held in Vienna from 8-12 April 1996. Refs, figs, tabs

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

Energy Technology Data Exchange (ETDEWEB)

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

1988-07-01

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

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

International exchange of safety and licensing information

International Nuclear Information System (INIS)

Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

1977-01-01

A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the U.S. Nuclear Regulatory Commission. For developing countries, such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that NRC has accumulated. NRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the NRC is in providing for reciprocal communicaion, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly-discovered problem in a nuclear reactor be brought immediately to the attention of other governments which are responsible for the safety of similar reactors. Definite progress has been made in the U.S. Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of NRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of country building its first power reactor is described

Nuclear Safety at the Ignalina NPP. Achievements and challenges. Proceedings of the international conference

International Nuclear Information System (INIS)

1999-01-01

The International Conference was held on 8-9 April, 1999 in Vilnius. The aim of this conference - to offers specialists an excellent chance to get acquainted with Lithuania's experience and the work it has done in the area of nuclear safety. Also this conference will help to depoliticize the discussion of nuclear power plants

Electrochemical performance and safety features of high-safety lithium ion battery using novel branched additive for internal short protection

International Nuclear Information System (INIS)

Li Yuhan; Lee, Meng-Lun; Wang Fuming; Yang, Chang-Rung; Chu, Peter P.J.; Yau, Shueh-Lin; Pan, Jing-Pin

2012-01-01

Highlights: ► N-phenylmaleimide-containing branched oligomer has been employed as an additive in lithium cells. ► The branched oligomer additive enhances safety and cycling performance of Li ion battery. ► The highest temperature of branched oligomer-containing battery was only 85 °C in the nail penetration test. - Abstract: In this study, we have investigated N-phenylmaleimide/bismaleimide-containing branched oligomer (BO1) as additive in Li-ion batteries to increase the safety performance by reducing the probability of batteries suffering an internal short circuit. In the nail penetration test, a LiCoO 2 /MCMB full battery with N-phenylmaleimide/bismaleimide-containing branched oligomer (BO1) showed a significant improvement in thermal stability and was able to restrain the temperature of the battery at about 85 °C. Furthermore, we found that N-phenylmaleimide/bismaleimide-containing branched oligomer (BO1) contained battery revealed better cycling and electrochemical performance, compared with the battery with bismaleimide-containing branched oligomer (BO3) in the electrolyte. The improvement might result from the favorable ionic conductivity, Li ion mobility and lower resistance in the battery. This additive can meet the cycling performance and safety requirements for Li-ion batteries.

International regulations on labour health and safety applied to fishing and maritime transport sectors. Are maritime workers under-protected.

Science.gov (United States)

Rodríguez, Julio Louro; Portela, Rosa Mary de la Campa; Pardo, Guadalupe Martín

2012-01-01

The work activity developed on board is of great importance in our nearby environment, and it has a series of peculiarities that determine the service rendering of sea workers. On the other hand, work at sea is developed on an international basis. Nowadays such work becomes a completely globalised industrial sector in relation to the elements that make up the ship's operation, including manpower. For that reason several relevant international organisations have paid attention to this industrial sector and have adopted a broad regulation on this matter. In the case of the European Union, the Community procedure emphasises enormous interest in providing specific and comprehensive training to seafarers, as well as in regulating working time on board with the aim of minimising the safety problems caused by fatigue. In the present article a schematic presentation of regulations on workers' health and occupational safety protection derived from the European Union, the International Maritime Organisation, and the International Labour Organisation has been done. Also it shows what parts of these regulations are not applicable to the work on board, and it reveals how the workers of fishing and maritime transport sectors are under-protected with regard to the guarantee of their health and occupational safety compared to workers in other sectors.

Maintaining knowledge, training and infrastructure for research and development in nuclear safety - INSAG-16. A report by the International Nuclear Safety Advisory Group

International Nuclear Information System (INIS)

2003-01-01

The purpose of this report is to emphasize the importance of maintaining capabilities for nuclear research and education, especially with regard to safety aspects, so that nuclear safety may be maintained in IAEA Member States, and to alert Member States to the potential for significant harm if the infrastructure for research, development and education is not maintained. If the infrastructure for nuclear safety is not maintained, there will be a steady decrease in expertise, and thus in capability to respond to new challenges. The lead time in developing replacement educational opportunities is very long, because most institutions will require an indication of the number of enthusiastic potential students before investing in new infrastructure, and potential students may look elsewhere in the absence of an exciting analytical and experimental programme and a growing career field. Once lost, it would require massive inputs of resources from many IAEA Member States to attempt to re-establish the infrastructure, as was done to establish it when nuclear technology was new. The result could be a downward spiral in which expertise is lost, influence of the technical community on the decision making process is diminished, and complacency, fed by diminished technical capability, begins to exert a strong effect. In view of the above, INSAG has the following recommendations: In order to maintain and further enhance the safety of nuclear facilities and to protect workers and the public and the environment from radiological consequences, the infrastructure for safety research (experimental facilities, highly competent staff and modern analytical tools) must be maintained and supported by the responsible governmental organizations as well as by the operating organizations and manufacturers. This support should include international networking and co-operation, including joint funding of centres of excellence that have facilities and equipment for use in nuclear research

Chapter No.4. Safety analyses

International Nuclear Information System (INIS)

2002-01-01

In 2001 the activity in the field of safety analyses was focused on verification of the safety analyses reports for NPP V-2 Bohunice and NPP Mochovce concerning the new profiled fuel and probabilistic safety assessment study for NPP Mochovce. The calculation safety analyses were performed and expert reviews for the internal UJD needs were elaborated. An important part of work was performed also in solving of scientific and technical tasks appointed within bilateral projects of co-operation between UJD and its international partnership organisations as well as within international projects ordered and financed by the European Commission. All these activities served as an independent support for UJD in its deterministic and probabilistic safety assessment of nuclear installations. A special attention was paid to a review of probabilistic safety assessment study of level 1 for NPP Mochovce. The probabilistic safety analysis of NPP related to the full power operation was elaborated in the study and a contribution of the technical and operational improvements to the risk decreasing was quantified. A core damage frequency of the reactor was calculated and the dominant initiating events and accident sequences with the major contribution to the risk were determined. The target of the review was to determine the acceptance of the sources of input information, assumptions, models, data, analyses and obtained results, so that the probabilistic model could give a real picture of the NPP. The review of the study was performed in co-operation of UJD with the IAEA (IPSART mission) as well as with other external organisations, which were not involved in the elaboration of the reviewed document and probabilistic model of NPP. The review was made in accordance with the IAEA guidelines and methodical documents of UJD and US NRC. In the field of calculation safety analyses the UJD activity was focused on the analysis of an operational event, analyses of the selected accident scenarios

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

Report on the second Congress of the Russian nuclear medicine society and on International conference Current problems of nuclear medicine and radiopharmaceuticals

International Nuclear Information System (INIS)

Lishmanov, Yu.B.; Chernov, V.I.

2001-01-01

Information on the work of Second Congress of Russian Nuclear Medicine Society and International Conference - Current problems of nuclear medicine and radiopharmaceuticals, - held in Obninsk in October, 2000, is adduced. Reports presented in the conference are dedicated to various aspects of application of radionuclide methods to cardiology, angiology, oncology, surgery, hematology, endocrinology, pediatrics and neurology. Problems in the development of radiopharmaceutical, training and skill advancement of experts, dosimetry and radiation safety in nuclear medicine were discussed. Congress considered the organizational problems in Russian nuclear medicine [ru

Safety culture

International Nuclear Information System (INIS)

1991-01-01

The response to a previous publication by the International Nuclear Safety Advisory Group (INSAG), indicated a broad international interest in expansion of the concept of Safety Culture, in such a way that its effectiveness in particular cases may be judged. This report responds to that need. In its manifestation, Safety Culture has two major components: the framework determined by organizational policy and by managerial action, and the response of individuals in working within and benefiting by the framework. 1 fig

France - convention on nuclear safety. Fifth national report for the 2011 peer review meeting

International Nuclear Information System (INIS)

2010-01-01

The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 in order to contribute maintaining a high level of nuclear safety worldwide. The convention aims to propose binding international obligations regarding nuclear safety. France signed the Convention on 20 September 1994, the date on which it was opened for signature during the IAEA's General Conference, and approved it on 13 September 1995. The Convention entered into force on 24 October 1996. For many years France has been participating actively in international initiatives to enhance nuclear safety, and it considers the Convention on Nuclear Safety to be an important instrument for achieving this aim. The areas covered by the Convention have long been part of the French approach to nuclear safety. The purpose of this fifth report, which was drafted pursuant to Article 5 of the Convention on Nuclear Safety, is to present the measures taken by France in order to fulfil each of her obligations as specified in the said Convention. Since the Convention applies to all nuclear-power generating reactors, most of this report is dedicated to the measures taken in order to ensure their safety. However, as in previous reports, France has decided to present also in this fifth report, the measures that were taken for all research reactors, together with a graduated approach, if need be, for taking their size into account. First of all, research reactors are actually submitted to the same overall regulations as nuclear-power reactors with regard to safety and radiation protection. It should be noted that the most powerful French research reactor, called Phenix, which also used to produce electricity, was disconnected from the grid in March 2009, but continued to run an 'ultimate-test programme' until 1 February 2010. Later, in the framework of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive

Reflections on a future international convention on safety in radioactive waste management - September 1994

International Nuclear Information System (INIS)

Arias Canete, A.

1995-01-01

This probably is a suitable moment for work to begin on an international Convention in this area, although it is a difficult task. Generally speaking, the RADWASS (Radioactive Waste Safety Standards) Programme has achieved sufficient consensus, and might serve as an important basis for work in relation to the Convention. The Convention should not go into highly technical details since consensus at this level is more difficult at the present moment, although this will undoubtedly be achieved in the medium term. An important element of the Convention should be the regulation of movements of radioactive wastes at international level. (orig./HP)

International recommendations for national patient safety incident reporting systems: an expert Delphi consensus-building process.

Science.gov (United States)

Howell, Ann-Marie; Burns, Elaine M; Hull, Louise; Mayer, Erik; Sevdalis, Nick; Darzi, Ara

2017-02-01

Patient safety incident reporting systems (PSRS) have been established for over a decade, but uncertainty remains regarding the role that they can and ought to play in quantifying healthcare-related harm and improving care. To establish international, expert consensus on the purpose of PSRS regarding monitoring and learning from incidents and developing recommendations for their future role. After a scoping review of the literature, semi-structured interviews with experts in PSRS were conducted. Based on these findings, a survey-based questionnaire was developed and subsequently completed by a larger expert panel. Using a Delphi approach, consensus was reached regarding the ideal role of PSRSs. Recommendations for best practice were devised. Forty recommendations emerged from the Delphi procedure on the role and use of PSRS. Experts agreed reporting system should not be used as an epidemiological tool to monitor the rate of harm over time or to appraise the relative safety of hospitals. They agreed reporting is a valuable mechanism for identifying organisational safety needs. The benefit of a national system was clear with respect to medication error, device failures, hospital-acquired infections and never events as these problems often require solutions at a national level. Experts recommended training for senior healthcare professionals in incident investigation. Consensus recommendation was for hospitals to take responsibility for creating safety solutions locally that could be shared nationally. We obtained reasonable consensus among experts on aims and specifications of PSRS. This information can be used to reflect on existing and future PSRS, and their role within the wider patient safety landscape. The role of PSRS as instruments for learning needs to be elaborated and developed further internationally. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

Is road safety management linked to road safety performance?

Science.gov (United States)

Papadimitriou, Eleonora; Yannis, George

2013-10-01

This research aims to explore the relationship between road safety management and road safety performance at country level. For that purpose, an appropriate theoretical framework is selected, namely the 'SUNflower' pyramid, which describes road safety management systems in terms of a five-level hierarchy: (i) structure and culture, (ii) programmes and measures, (iii) 'intermediate' outcomes'--safety performance indicators (SPIs), (iv) final outcomes--fatalities and injuries, and (v) social costs. For each layer of the pyramid, a composite indicator is implemented, on the basis of data for 30 European countries. Especially as regards road safety management indicators, these are estimated on the basis of Categorical Principal Component Analysis upon the responses of a dedicated road safety management questionnaire, jointly created and dispatched by the ETSC/PIN group and the 'DaCoTA' research project. Then, quasi-Poisson models and Beta regression models are developed for linking road safety management indicators and other indicators (i.e. background characteristics, SPIs) with road safety performance. In this context, different indicators of road safety performance are explored: mortality and fatality rates, percentage reduction in fatalities over a given period, a composite indicator of road safety final outcomes, and a composite indicator of 'intermediate' outcomes (SPIs). The results of the analyses suggest that road safety management can be described on the basis of three composite indicators: "vision and strategy", "budget, evaluation and reporting", and "measurement of road user attitudes and behaviours". Moreover, no direct statistical relationship could be established between road safety management indicators and final outcomes. However, a statistical relationship was found between road safety management and 'intermediate' outcomes, which were in turn found to affect 'final' outcomes, confirming the SUNflower approach on the consecutive effect of each layer

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

Emerging trends in PHWR safety - post Fukushima measures

International Nuclear Information System (INIS)

Nitheanandan, T.

2015-01-01

Nuclear power continues to be the choice for many countries that are seeking to enhance their energy security and reduce their carbon emissions. Nuclear power plants are complex systems which require multiple layers of protection. The fundamental principle of nuclear power safety technology is ‘Defence-in-Depth’ that underlies all safety activities - organizational, behavioural and technical. This provides layers of overlapping barrier protections so that, in the unlikely event that failure occurs, it would be compensated or corrected without causing harm to individuals or the public at large. Defence-in-depth encompasses prevention, control, protection, severe accident management and consequence mitigation, and offsite emergency response measures. Reactor Safety Science and Technology (S and T) has evolved over more than four decades in a number of PHWR countries. The PHWR operators, regulators and national research laboratories have dedicated S and T programs to continuously improve plant safety, operations and margins. The S and T is focused on finding simpler, less costly and more reliable safety system designs. These improvements are continuously incorporated in current units, refurbished units and proposed new builds. The Fukushima accident forced most nuclear nations to reassess and implement reactor design upgrades. The lessons learned from Fukushima have generated some nuclear safety enhancements such as: Design considerations for natural hazards, Diversity of heat sinks, Consideration of extended duration station blackout, Improvements to Severe Accident Management and SAM Operational aids, Accident instrumentation, Offsite management such as the use of predictive exposure tools, and Design considerations for Spent Fuel Pools. The plenary presentation will provide some of the emerging trends following the Fukushima accident. Examples of these emerging trends in Canada and on the international scene, will be presented. (author)

Accessing International Funding for Climate Change Adaptation

DEFF Research Database (Denmark)

Christiansen, Lars; Ray, Aaron D.; Smith, Joel B.

of international public funding sources dedicated to adaptation investments (Chapter 3) • Seven fundamental eligibility criteria for accessing international public funding and guidance on how to apply these concepts to project ideas (Chapter 3) • A template (built on the abovementioned seven fundamental...

Domain 2: Sport Safety and Injury Prevention

Science.gov (United States)

Gurchiek, Larry; Mokha, Monique Butcher

2004-01-01

Most coaches recognize the importance of creating a safe environment and preventing injuries of their athletes. Domain 2 is dedicated to this important aspect of coaching, and outlines specific areas within safety and injury prevention that coaches should address. Domain 2 sets the standards for facility, equipment, and environmental safety…

International exchange of safety and licensing information

International Nuclear Information System (INIS)

Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

1977-01-01

A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the US Nuclear Regulatory Commission. For developing countries such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that USNRC has accumulated. USNRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the USNRC is in providing for reciprocal communication, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly discovered problem in a nuclear reactor be brought immediately to the attention of other governments that are responsible for the safety of similar reactors. Definite progress has been made in the USA in defining categories of information that USNRC can receive in confidence from foreign countries, and can protect from disclosure under the US Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of USNRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of a country building its first power reactor is described. (author)

Radiation safety

International Nuclear Information System (INIS)

1996-04-01

Most of the ionizing radiation that people are exposed to in day-to-day activities comes from natural, rather than manmade, sources. The health effects of radiation - both natural and artificial - are relatively well understood and can be effectively minimized through careful safety measures and practices. The IAEA, together with other international and expert organizations, is helping to promote and institute Basic Safety Standards on an international basis to ensure that radiation sources and radioactive materials are managed for both maximum safety and human benefit

Statement to the International Conference on the Safety of Transport of Radioactive Material. Vienna, 7 July 2003

International Nuclear Information System (INIS)

ElBaradei, M.

2003-01-01

The transport of radioactive material has been subject to regulation for many decades, and the International Atomic Energy Agency, working with its Member States and all relevant international governmental organizations, has played a key role in fostering the establishment of those regulations and providing for their application. First published in 1961, the IAEA's Regulations for the Safe Transport of Radioactive Material are periodically revised to incorporate technical advances, operational experience and the latest radiation protection principles. These Transport Regulations address all categories of radioactive material. Although recommendatory in nature, they constitute the basis for national regulations in many Member States, and generally become mandatory through the legally binding instruments of the relevant modal bodies, such as the International Maritime Organization or the International Civil Aviation Organization. In some cases, these instruments take the form of universal conventions, such as the Convention on International Civil Aviation or the International Convention for the Safety of Life at Sea; in other cases, they take the form of regional agreements, such as the European Agreement Concerning the International Carriage of Dangerous Goods by Road. Overall, there are 21 universal instruments and 22 regional instruments in force that apply, directly or indirectly, to the safe transport of radioactive material. This current worldwide system of regulatory control, while not without shortcomings, has achieved an excellent safety record. Over several decades of transporting radioactive material, there has not been an in-transit accident with serious human health, economic or environmental consequences attributable to the radioactive nature of the transported goods. In recognition of this fact, the United Nations Committee on the Effects of Atomic Radiation has noted these transport activities as having no radiological impact. This excellent record

Safety of Cargo Aircraft Handling Procedure

Directory of Open Access Journals (Sweden)

Daniel Hlavatý

2017-07-01

Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

Uranium Production Safety Assessment Team. UPSAT. An international peer review service for uranium production facilities

International Nuclear Information System (INIS)

1996-01-01

The IAEA Uranium Production Safety Assessment Team (UPSAT) programme is designed to assist Member States to improve the safe operation of uranium production facilities. This programme facilitates the exchange of knowledge and experience between team members and industry personnel. An UPSAT mission is an international expert review, conducted outside of any regulatory framework. The programme is implemented in the spirit of voluntary co-operation to contribute to the enhancement of operational safety and practices where it is most effective, at the facility itself. An UPSAT review supplements other facility and regulatory efforts which may have the same objective

Introduction of the commercial grade dedication into Nuclear Power Plant Krsko (NEK) procurement process

International Nuclear Information System (INIS)

Heruc, Z.; Gajsak, Z.; Nikpalj, R.

1996-01-01

NEK management has undertaken a set of actions to improve the ability to provide equipment, spare parts and material needed to support operation and maintenance of the Krsko plant. These actions are necessary due primarily to the fact that NEK is more and more confronted (increasing trend) with the issue that suppliers of safety-related equipment and spare parts have decided not to pursue the nuclear portion of their business, incl. specific QA systems and qualifications. The purchase orders imposing these requirements are no longer accepted. In order to continue to obtain the necessary materials at the required quality level, a 'Commercial Grade Item' (CGI) procurement and dedication program has been developed based on similar practices in USA. (author)

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

Status and trends in IAEA safety standards

International Nuclear Information System (INIS)

Lipar, M.

2004-01-01

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

Safety study of the coupling of a VHTR with a hydrogen production plant

International Nuclear Information System (INIS)

Bertrand, F.; Germain, T.; Bentivoglio, F.; Bonnet, F.; Moyart, Q.; Aujollet, P.

2011-01-01

Highlights: → The paper deals with safety issues of the coupling of a VHTR with a H 2 production plant. → Internal incidents/accidents in the coupling system have been studied with the CATHARE2 code. → Transient studies have indicated a substantial grace delay when the VHTR faces the H 2 plant disturbances. → Hydrogen release and combustion leads to safety distances of about 100 m. → No showstopper has been put in evidence regarding the feasibility of the VHTR/H 2 plant coupling. - Abstract: The present paper deals with specific safety issues resulting from the coupling of a nuclear reactor (very high temperature reactor, VHTR) with a hydrogen production plant (HYPP). The first part is devoted to the safety approach consisting in taking into account the safety standards and rules dedicated to the nuclear facility as well as those dedicated to the process industry. This approach enabled two main families of events to be distinguished: the so-called internal events taking place in the coupling circuit (transients, breaks in pipes and in heat exchangers) and the external events able to threat the integrity of the various equipments (in particular the VHTR containment and emergency cooling system) that could result from accidents in the HYPP. By considering a hydrogen production by means of the iodine/sulfur (IS) process, the consequences of the both families of events aforementioned have been assessed in order to provide an order of magnitude of the effects of the incidents and accidents and also in order to propose safety provisions to mitigate these effects when it is necessary. The study of transients induced by a failure of a part of the HYPP has shown the possibility to keep the part of the HYPP unaffected by the transient under operation by means of an adapted regulation set. Moreover, the time to react in case of transfer of corrosive products in the VHTR containment has been assessed as well as the thermohydraulic loading that would experience the

Safety in nuclear technology through introduction of internationally binding agreements

International Nuclear Information System (INIS)

1987-01-01

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

Investigation of occupational health and safety application using the internal and external factor assessment matrix: SWOT

Directory of Open Access Journals (Sweden)

2012-09-01

Material and Method: IIn this study, the threats, opportunities, weaknesses and strengths were evaluated by one of the tools named SWOT, in one of the assembly industries company in Iran, in order to controlling the operations in this company considering to safety and health standard (OHSAS18001. A comparison of the company’s performance in implementing the safety and health standards was done between years 1387 and 1388 contain in the Company considered, and weighted scoring weaknesses, strengths, threats and opportunities using the matrix of internal factors (strengths and weaknesses and external factors (treats and opportunities then, the importance of each factor were determined in the company’s implementation and enforcement of those standards. . Result: Focusing on the strengths and weaknesses, opportunities and threats, some strategies to improve the implementation were presented. Any points were weighted based on the most important weaknesses identified as the lack of monitoring contractors, lack of management commitment for implementation of OHSAS18001, no attempt to identify the risks of change, lack of training needs assessment, main strengths identified in the context of adequate budget health and safety, environmental efforts, identify risk for abnormal conditions, the most important threats for immediate delivery customer orders and the opportunity to support the safety and health plans, were determined. . Conclusion: Sum of the weighted scores in year 87 were obtained for the external factors (opportunities and threats, 2.16 and internal factors (strengths and weaknesses 1.66. Both of these scores were less than 2.5 (minimum amount of the acceptable rate so, the company has been poor performance in the implementation of this standard for the year 87 and a weak reaction in the use of opportunities and the minimize threats has. In case of internal factors, it was worse than external one and the situation was more bold of the weaknesses companies to

International co-operation in safety matters within the framework of the Commission of the European Communities

International Nuclear Information System (INIS)

Vinck, W.; Balz, W.; Essler, W.; Tolley, B.; Gabolde, J.

1981-01-01

European Community (EC) countries realize that their energy demand cannot be met without a nuclear component, which is almost a necessity owing to its major economic advantages. Two typical areas where the Commission has stimulated intense international co-operation are as follows: The first broad area deals with efforts towards a gradual harmonization of regulatory health and safety practices and requirements for reactors of an industrially developed type, more specifically (light) water-cooled reactors. The second area concerns joint research programmes and co-ordination activities in research on nuclear safety (LWRs and LMFBRs). These two broad areas are closely interconnected. Information is also given on the existing network of bilateral and multilateral arrangements for the exchange of information of interest to the EC. In conclusion, some problems are highlighted where improvements could be made or where it seems crucial that increased international co-operation and especially agreement should come about. (author)

The Impact of a Dedicated Research Education Month for Anesthesiology Residents

Directory of Open Access Journals (Sweden)

Robert E. Freundlich

2015-01-01

Full Text Available An educational intervention was implemented at the University of Michigan starting in 2008, in which anesthesiology interns complete a dedicated month-long didactic rotation in evidence-based medicine (EBM and research methodology. We sought to assess its utility. Scores on a validated EBM test before and after the rotation were compared and assessed for significance of improvement. A survey was also given to gauge satisfaction with the quality of the rotation and self-reported improvement in understanding of EBM topics. Fourteen consecutive interns completed the research rotation during the study period. One hundred percent completed both the pre- and postrotation test. The mean pretest score was 7.78 ± 2.46 (median = 7.5, 0–15 scale, and interquartile range 7.0–10.0 and the mean posttest score was 10.00 ± 2.35 (median = 9.5, interquartile range 8.0–12.3, which represented a statistically significant increase (P=0.011, Wilcoxon signed-rank test. All fourteen of the residents “agreed” or “strongly agreed” that they would recommend the course to future interns and that the course increased their ability to critically review the literature. Our findings demonstrate that this can be an effective means of improving understanding of EBM topics and anesthesiology research.

On the development of an International Curriculum on Hydrogen Safety Engineering and its Implementation into Educational Programmes

International Nuclear Information System (INIS)

Dahoe, A.E.; Molkov, V.V.

2006-01-01

The present paper provides an overview of the development of an International Curriculum on Hydrogen Safety Engineering and its implementation into new educational programmes. The curriculum has a modular structure, and consists of five basic, six fundamental and four applied modules. The reasons for this particular structure are explained. To accelerate the development of teaching materials and their implementation in training/educational programmes, an annual European Summer School on Hydrogen Safety will be held (the first Summer School is from 15-24 Aug 2006, Belfast, UK), where leading experts deliver keynote lectures to an audience of researchers on topics covering the state-of-the-art in Hydrogen Safety Science and Engineering. The establishment of a Postgraduate Certificate course in Hydrogen Safety Engineering at the University of Ulster (starting in September 2006) as a first step in the development of a worldwide system of Hydrogen Safety education and training is described. (authors)

Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

International Nuclear Information System (INIS)

2004-05-01

Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

An International Peer Review of the Safety Options Dossier of the Project for Disposal of Radioactive Waste in Deep Geological Formations (Cigéo). Final Report of the IAEA International Review Team November 2016

International Nuclear Information System (INIS)

2017-07-01

The French Nuclear Safety Authority (Autorité de sûreté nucléaire, ASN) is preparing the evaluation of a licence application for the creation of a deep geological disposal facility in 2018, called Cigéo, for intermediate level, high level and long lived radioactive waste. This licence is preceded by the submission of a Safety Options Dossier to ASN, which provides the French National Radioactive Waste Management Agency (Agence nationale pour la gestion des déchets radioactifs, Andra) the possibility to receive advice from ASN on the preparation of the licence application on the safety principles and approach. The Safety Options Dossier sets out the chosen objectives, concepts and principles for ensuring the safety of the facility. ASN requested the IAEA to organize an international peer review of the Safety Options Dossier. This publication presents the consensus view of the international group of experts convened by the IAEA to conduct the review against the relevant IAEA safety standards and proven international practice and experience. The experts acted in a personal capacity and the views expressed do not necessarily reflect those of the IAEA, the governments of the nominating Member States or the nominating organizations. The basis of this peer review is the set of documents provided by Andra, as the agency responsible for the development of the Cigéo project and for its safety. Consequently, the findings of the reviews are addressed directly to Andra. This publication, however, is primarily submitted to ASN to review the outcomes of the Andra project.

III International Conference on Small Angle Neutron Scattering dedicated to the 80 anniversary of Yu.M. Ostanevich

International Nuclear Information System (INIS)

2017-01-01

Preface “Among the many well-known fundamental and applied consequences of neutron discovery, one of the first was the emergence of structural neutron diffraction - one of the methods for studying the spatial structure of condensed matter at the atomic level. Investigating the dynamics of biological macromolecules by neutron diffraction methods is an area that is almost untouched. We believe that also in this direction one should expect rapid progress.” Yu.M.Ostanevich and I.N.Serdyuk Uspekhi Fizicheskih Nauk (1982) More than 30 years after Ostanevich and Serdyuk reviewed the then 50 years from the neutron discovery, we are happy to support their statement and prediction by reporting on the further progress in the field of neutron scattering research. Frank Laboratory of Neutron Physics has organized the III International Conference on Small Angle Neutron Scattering (YuMO2016) that was – not coincidently – dedicated to the 80th anniversary of Ostanevich. Yuriy Mechislavovich Ostanevich (1936–1992) has had a determinative and crucial contribution to the construction of spectrometers at the pulsed reactor IBR in Dubna, Russia. He contributed in particular to the development of time-of-flight small-angle neutron scattering (SANS) technique, and the selection of advanced scientific areas for its application. The SANS instrument at the IBR-2 reactor is called YuMO in his honour. The Ostanevich’s leadership and outstanding scientific achievements in SANS studies of polyelectrolytes, small molecules, fractals, metallic glasses, macromolecules, polymers, etc., were recognized also by a number of awards including the State Prize of the Russian Federation in 2000. To this end of course, we should not forget mentioning the contribution of close collaborators of Ostanevich: Laszlo Cser, Josef Plestil as well as Alexander Kunchenko, Vadim Bezzabotnov and Nikolay Gorski. The YuMO2016 conference focused on providing opportunities to discuss various possibilities of

Safety Climate, Perceived Risk, and Involvement in Safety Management

OpenAIRE

Kouabenan , Dongo Rémi; Ngueutsa , Robert ,; Safiétou , Mbaye

2015-01-01

International audience; This article examines the relationship between safety climate, risk perception and involvement in safety management by first-line managers (FLM). Sixty-three FLMs from two French nuclear plants answered a questionnaire measuring perceived workplace safety climate, perceived risk, and involvement in safety management. We hypothesized that a positive perception of safety climate would promote substantial involvement in safety management, and that this effect would be str...

International Cooperation in the Field of International Space Station Payload Safety: Overcoming Differences and Working for Future

Science.gov (United States)

Nakamura, Yasuhiro; Ozawa, Masayuki; Takeyasu, Yoshioka; Griffith, Gerald; Goto, Katsuhito; Mitsui, Masami

2010-09-01

The importance of international cooperation among the International Space Station(ISS) Program participants is ever increasing as the ISS nears assembly complete. In the field of payload safety assurance, NASA and JAXA have enhanced their cooperation level. The authors describe the evolution of cooperation between the two agencies and the challenges encountered and overcame. NASA and JAXA have been working toward development of a NASA Payload Safety Review Panel(PSRP) franchise panel at JAXA for several years. When the JAXA Safety Review Panel(SRP) becomes a fully franchised panel of the NASA PSRP, the JAXA SRP will have the authority review and approve all JAXA ISS payloads operated on USOS and JEM, although NASA and JAXA joint reviews may be conducted as necessary. A NASA PSRP franchised panel at JAXA will streamline the conventional review process. Japanese payload organizations will not have to go through both JAXA and NASA payload safety reviews, while NASA will be relieved of a certain amount of review activities. The persistent efforts have recently born fruit. For the past two years, NASA and JAXA have increased emphasis on efforts to develop a NASA PSRP Franchised Panel at JAXA with concrete results. In 2009, NASA and JAXA signed Charter and Joint Development Plan. At the end of 2009, NASA PSRP transferred some review responsibility to the JAXA SRP under the franchising charter. Although JAXA had long history of reviewing payloads by their own panel prior to NASA PSRP reviews, it took several years for JAXA to receive NASA PSRP approval for delegation of franchised review authority to JAXA. This paper discusses challenges JAXA and NAXA faced. Considerations were required in developing a franchise at JAXA for history and experiences of the JAXA SRP as well as language and cultural differences. The JAXA panel, not only had its own well-established processes and supporting organizational structures which had some differences from its NASA PSRP counterparts

Nuclear safety, international cooperation and perspectives of Bulgaria; Yadernaya bezopasnost`, mezhdunarodnoe sotrudnichestvo i perspektivy dlya Bolgarii

Energy Technology Data Exchange (ETDEWEB)

Yanev, Y

1996-12-31

The use of atomic energy in Bulgaria is under regulation since 1985 by the Atomic Energy Law. The main points of the Law are discussed and some deficiencies are pointed out. The ratification of the Vienna and Paris conventions has contributed to updating the legislation. The participation in international projects related to the use of atomic energy and nuclear safety in particular is revised. Future development of nuclear energy in Bulgaria depends mainly on successful reconstruction, modernization and safety enhancement of the Kozloduy NPP and development of a national grid of technical and consultant firms.

Commissioning of research reactors. Safety guide

International Nuclear Information System (INIS)

2006-01-01

The objective of this Safety Guide is to provide recommendations on meeting the requirements for the commissioning of research reactors on the basis of international best practices. Specifically, it provides recommendations on fulfilling the requirements established in paras 6.44 and 7.42-7.50 of International Atomic Energy Agency, Safety of Research Reactors, IAEA Safety Standards Series No. NS-R-4, IAEA, Vienna (2005) and guidance and specific and consequential recommendations relating to the recommendations presented in paras 615-621 of International Atomic Energy Agency, Safety in the Utilization and Modification of Research Reactors, Safety Series No. 35-G2, IAEA, Vienna (1994) and paras 228-229 of International Atomic Energy Agency, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, Safety Series No. 35-G1, IAEA, Vienna (1994). This Safety Guide is intended for use by all organizations involved in commissioning for a research reactor, including the operating organization, the regulatory body and other organizations involved in the research reactor project

GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

Energy Technology Data Exchange (ETDEWEB)

Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

2015-07-01

International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

BFS, a Legacy to the International Reactor Physics, Criticality Safety, and Nuclear Data Communities

International Nuclear Information System (INIS)

Briggs, J. Blair; Tsibulya, Anatoly; Rozhikhin, Yevgeniy

2012-01-01

Interest in high-quality integral benchmark data is increasing as efforts to quantify and reduce calculational uncertainties accelerate to meet the demands of next generation reactor and advanced fuel cycle concepts. Two Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) activities, the International Criticality Safety Benchmark Evaluation Project (ICSBEP), initiated in 1992, and the International Reactor Physics Experiment Evaluation Project (IRPhEP), initiated in 2003, have been identifying existing integral experiment data, evaluating those data, and providing integral benchmark specifications for methods and data validation for nearly two decades. Thus far, 14 countries have contributed to the IRPhEP, and 20 have contributed to the ICSBEP. Data provided by these two projects will be of use to the international reactor physics, criticality safety, and nuclear data communities for future decades The Russian Federation has been a major contributor to both projects with the Institute of Physics and Power Engineering (IPPE) as the major contributor from the Russian Federation. Included in the benchmark specifications from the BFS facilities are 34 critical configurations from BFS-49, 61, 62, 73, 79, 81, 97, 99, and 101; spectral characteristics measurements from BFS-31, 42, 57, 59, 61, 62, 73, 97, 99, and 101; reactivity effects measurements from BFS-62-3A; reactivity coefficients and kinetics measurements from BFS-73; and reaction rate measurements from BFS-42, 61, 62, 73, 97, 99, and 101.

Fusion reactor safety

International Nuclear Information System (INIS)

1987-12-01

Nuclear fusion could soon become a viable energy source. Work in plasma physics, fusion technology and fusion safety is progressing rapidly in a number of Member States and international collaboration continues on work aiming at the demonstration of fusion power generation. Safety of fusion reactors and technological and radiological aspects of waste management are important aspects in the development and design of fusion machines. In order to provide an international forum to review and discuss the status and the progress made since 1983 in programmes related to operational safety aspects of fusion reactors, their waste management and decommissioning concepts, the IAEA had organized the Technical Committee on ''Fusion Reactor Safety'' in Culham, 3-7 November 1986. All presentations of this meeting were divided into four sessions: 1. Statements on National-International Fusion Safety Programmes (5 papers); 2. Operation and System Safety (15 papers); 3. Waste Management and Decommissioning (5 papers); 4. Environmental Impacts (6 papers). A separate abstract was prepared for each of these 31 papers. Refs, figs, tabs

The Iranian Atomic program - Energy- versus Safety policy? On the problem of international non-proliferation regime

International Nuclear Information System (INIS)

Klimas, Mirko

2007-01-01

The Iranian atomic program: An important part of national energy policy or military way out of the international safety dilemma? In detail the author investigates - against background of Neorealism Theory - the coherences between international non-proliferation regimes - from Atoms for Peace program of the 1950 years up to actual measures of the IAEA - and the development of the Iranian atomic program. Off from superficial discussions on intentions of the Iranian government the book lightens the background of an international policy, which not only favours Iran during production of nuclear weapons as also invites the country to a military utilization of its atomic program. (orig./GL)

French nuclear safety authorities: for a harmonization of nuclear safety at the European level

International Nuclear Information System (INIS)

Anon.

2004-01-01

The European Commission is working on 2 directives concerning nuclear energy: the first one is dedicated to nuclear safety and the second to the management of radioactive wastes and spent fuels. In the context of the widening of the European Union and of the inter-connection of the different electric power grids throughout Europe, the harmonization of the rules in the nuclear safety field is seen by manufacturers as a mean to achieve a fair competition between nuclear equipment supplying companies and by the French nuclear safety authorities (FNSA) as a mean to keep on improving nuclear safety and to be sure that competitiveness does not drive safety standards down. According to FNSA the 2 European directives could give a legal framework to the harmonization and should contain principles that reinforce the responsibility of each state. FNSA considers that the EPR (European pressurized water reactor) may be an efficient tool for the harmonization because of existing industrial cooperation programs between France and Germany and between France and Finland. (A.C.)

An international review of patient safety measures in radiotherapy practice

International Nuclear Information System (INIS)

Shafiq, Jesmin; Barton, Michael; Noble, Douglas; Lemer, Claire; Donaldson, Liam J.

2009-01-01

Errors from radiotherapy machine or software malfunction usually are well documented as they affect hundreds of patients, whereas random errors affecting individual patients are more difficult to be discovered and prevented. Although major clinical radiotherapy incidents have been reported, many more have remained unrecognised or have not been reported. The literature in this field is limited as it is mostly published as a result of investigation of major errors. We present a review of radiotherapy incidents internationally with the aim of identifying the domains where most errors occur through extensive review and synthesis of published reports, unpublished 'Grey literature' and departmental incident data. Our review of radiotherapy-related events in the last three decades (1976-2007) identified more than seven thousand (N = 7741) incidents and near misses. Three thousand one hundred and twenty-five incidents reported patient harm of variable intensity ranging from underdose increasing the risk of recurrence, to overdose causing toxicity, and even death for 1% (N = 38); 4616 events were near misses with no recognisable patient harm. Based on our review, a radiotherapy risk profile has been published by the WHO World Alliance for Patient Safety that highlights the role of communication, training and strict adherence to guidelines/protocols in improving the safety of radiotherapy process.

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

Global Food Safety?International Consumers? Rights?

OpenAIRE

Hussain, Malik Altaf

2013-01-01

Your submissions to this Special Issue “Food Microbiology and Safety” of Foods—a new open access journal—are welcome. We understand there are no foodborne illness-free zones in the world. Therefore, a proper understanding of foodborne pathogens and the factors that impact their growth, survival and pathogenesis would equip us with tools to ensure global food safety. This Special Issue publishes articles on different aspects of food microbiology and safety.

International Expert Team Concludes IAEA Peer Review of Slovakia's Regulatory Framework for Nuclear Safety

International Nuclear Information System (INIS)

2012-01-01

Full text: An international team of senior nuclear safety and radiation protection experts today concluded an 11-day mission to review the regulatory framework for nuclear safety in Slovakia. At the request of the Slovak Government, the IAEA assembled a team of 12 senior regulatory experts from 12 nations to conduct the Integrated Regulatory Review Service (IRRS) mission involving the Nuclear Regulatory Authority of the Slovak Republic (UJD SR). The international experts also met officials from the Public Health Authority of the Slovak Republic (UVZ SR) regarding the regulation of occupational radiation protection in nuclear facilities. The mission is a peer review based on the IAEA Safety Standards. Marta Ziakova, Chairperson of the Nuclear Regulatory Authority of Slovak Republic, declared that ''The IRRS mission has a great value for the future development and orientation of the UJD SR.'' ''Slovakia has established a regulatory framework for nuclear safety which is in line with international standards and practice,'' said Mission Team Leader Andrej Stritar, Director of the Slovenian Nuclear Safety Administration. The main observations of the IRRS Review team included: UJD SR operates with independence and transparency; UJD SR has developed and implemented a systematic training approach to meet its competence needs; and in response to the accident at TEPCO's Fukushima Daiichi Nuclear Power Station, UJD SR has reacted and communicated to interested parties, including the public. The good practices identified by the IRRS Review Team include: UJD SR has a comprehensive and well-formalized strategic approach to informing and consulting interested parties; UJD SR has developed and implemented a structured approach to training and developing its staff; and Detailed legal requirements provide a solid basis for on-site and off-site response in nuclear emergencies coordinated with local authorities. The IRRS Review team identified areas for further improvement and believes

Operational safety - the IAEA response

International Nuclear Information System (INIS)

Rosen, M.

1984-01-01

Nuclear safety is an international issue. The role of the International Atomic Energy Agency is growing because it offers a centre for contact and exchange between East and West, North and South. New initiatives are under way to intensify international co-operative safety efforts through exchange of information on abnormal events at nuclear power plants, and through greater sharing of safety research results. Emergency preparedness also lends itself to international co-operation. A report has been prepared on the need for establishing mutual emergency assistance. By analysing possible constraints to bilateral or multinational efforts in advance, a basis for agreement at the time of an emergency is being worked out. Safety standards have been developed in several areas. The NUSS Codes and Guides, now almost complete, make available to countries starting a nuclear power programme a coherent set of nuclear safety standards. A revised set of Basic Safety Standards for Radiation Protection has been issued in 1982. (author)

Coherence in Professional Education: Does It Foster Dedication and Identification?

Science.gov (United States)

Heggen, Kåre; Terum, Lars Inge

2013-01-01

This article examines the impact of professional education on students' dedication to and identification with a profession. The premise is that professional education is not only about knowledge acquisition and reasoning but also about attitudes and aspirations. In fostering dedication and identification, students' experiences of relevance seem to…

Operating Dedicated Data Centers - Is It Cost-Effective?

Science.gov (United States)

Ernst, M.; Hogue, R.; Hollowell, C.; Strecker-Kellog, W.; Wong, A.; Zaytsev, A.

2014-06-01

The advent of cloud computing centres such as Amazon's EC2 and Google's Computing Engine has elicited comparisons with dedicated computing clusters. Discussions on appropriate usage of cloud resources (both academic and commercial) and costs have ensued. This presentation discusses a detailed analysis of the costs of operating and maintaining the RACF (RHIC and ATLAS Computing Facility) compute cluster at Brookhaven National Lab and compares them with the cost of cloud computing resources under various usage scenarios. An extrapolation of likely future cost effectiveness of dedicated computing resources is also presented.

International topical meeting. Research Reactor Fuel Management (RRFM) and meeting of the International Group on Reactor Research (IGORR)

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

Nuclear research and test reactors have been in operation for over 60 years, over 270 research reactors are currently operating in more than 50 countries. This meeting is dedicated to different aspects of research reactor fuels: new fuels for new reactors, the conversion to low enriched uranium fuels, spent fuel management and computational tools for core simulation. About 80 contributions are reported in this document, they are organized into 7 sessions: 1) international topics and overview on new projects and fuel, 2) new projects and upgrades, 3) fuel development, 4) optimisation and research reactor utilisation, 5) innovative methods in research reactors physics, 6) safety, operation and research reactor conversion, 7) fuel back-end management, and a poster session. Experience from Australian, Romanian, Libyan, Syrian, Vietnamese, South-African and Ghana research reactors are reported among other things. The Russian program for research reactor spent fuel management is described and the status of the American-driven program for the conversion to low enriched uranium fuels is presented. (A.C.)

Time evolution of the energy confinement time, internal inductance and effective edge safety factor on IR-T1 tokamak

International Nuclear Information System (INIS)

Salar Elahi, A; Ghoranneviss, M

2010-01-01

An attempt is made to investigate the time evolution of the energy confinement time, internal inductance and effective edge safety factor on IR-T1 tokamak. For this purpose, four magnetic pickup coils were designed, constructed and installed on the outer surface of the IR-T1 and then the Shafranov parameter (asymmetry factor) was obtained from them. On the other hand, also a diamagnetic loop was designed and installed on IR-T1 and poloidal beta was determined from it. Therefore, the internal inductance and effective edge safety factor were measured. Also, the time evolution of the energy confinement time was measured using the diamagnetic loop. Experimental results on IR-T1 show that the maximum energy confinement time (which corresponds to minimum collisions, minimum microinstabilities and minimum transport) is at low values of the effective edge safety factor (2.5 eff (a) i <0.72). The results obtained are in agreement with those obtained with the theoretical approach [1-5].

Static Safety for an Actor Dedicated Process Calculus by Abstract Interpretation

OpenAIRE

Garoche, Pierre-Loïc; Pantel, Marc; Thirioux, Xavier

2006-01-01

International audience; The actor model eases the definition of concurrent programs with non uniform behaviors. Static analysis of such a model was previously done in a data-flow oriented way, with type systems. This approach was based on constraint set resolution and was not able to deal with precise properties for communications of behaviors. We present here a new approach, control-flow oriented, based on the abstract interpretation framework, able to deal with communication of behaviors. W...

A dedicated pollution tax: The motor for change

International Nuclear Information System (INIS)

Stoyke, E.; Stoyke, G.

1992-01-01

Carbon taxes coming into effect around the world are predicted to reduce greenhouse gas emissions by 1-6%. Using the punitive approach alone, such taxes will not be sufficiently effective in fighting global climate change. A dedicated pollution tax is proposed in which moderate fees on greenhouse gases and other polluting emissions are balanced by financial incentives for energy efficient retrofitting or non-polluting substitutions. These incentives will vastly accelerate conversion to energy efficient technologies by reducing payback periods to acceptable levels and will lead to a 50-80% reduction in fossil fuel consumption at a profit. Estimated environmental costs of pollutant emissions from coal and natural gas are presented, and the internalization of external costs into energy prices is discussed. Demand reduction provides more environmental benefits than scrubbing of fossil emissions, at less cost. Examples of potential lighting savings in a classroom are presented, and simple payback and savings for a variety of lighting energy efficiency measures are tabulated. The effects of different pollution tax levels on Alberta's coal fired electricity generation are tabulated. 5 refs., 6 figs., 4 tabs

Use of electronic group method in assessing food safety training needs and delivery methods among international college students in the U.S.

Science.gov (United States)

Garden-Robinson, Julie; Eighmy, Myron A; Lyonga, Agnes Ngale

2010-12-01

The purpose of this study was to determine the types of unfamiliar foods international students in the U.S. encounter and to assess food safety information that international students would like to receive for mitigating risks associated with handling and preparing unfamiliar foods. The study identified preferred instructional delivery methods and media for receiving food safety training or information. An electronic group method was used for this study. The electronic group method was chosen to maximize group efficiency by allowing participants to share ideas simultaneously and anonymously with minimal use of time and resources.Types of different (unfamiliar) foods were grouped into major categories. Fast and ready-to-eat foods, and processed and frozen foods constituted a major change for some international students, who were accustomed to homemade and fresh foods in their countries. Participants were interested in receiving information about how to safely handle and prepare unfamiliar foods in their new environment. Preferred methods for receiving food safety information included written materials, online publications, presentations, and materials provided during student orientation. Food packages, websites, and television programs were other preferred methods of receiving food safety information. Copyright © 2010 Elsevier Ltd. All rights reserved.

Introduction of the commercial grade dedication into Nuclear Power Plant Krsko (NEK) procurement process

International Nuclear Information System (INIS)

Heruc, Z.; Gajsak, Z.; Nikpalj, R.

1996-01-01

NEK management has undertaken a set of actions to improve the ability to provide equipment, spare parts and material needed to support operation and maintenance of the Krsko plant. These actions are necessary due primarily to the fact that NEK is more and more confronted (increasing trend) with the issue that suppliers of safety-related equipment and spare parts have decided not to pursue the nuclear portion of their business, incl. specific QA systems and qualifications. The purchase orders imposing these requirements are no longer accepted. In order to continue to obtain the necessary materials at the required quality level, a 'Commercial Grade Item' (CGI) procurement and dedication program has been developed based on similar practices in the USA. (author)

Safety Assessment for Decommissioning

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-06-15

In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum

Maintaining knowledge, training and infrastructure for research and development in nuclear safety. INSAG-16. A report by the International Nuclear Safety Advisory Group (Russian Edition)

International Nuclear Information System (INIS)

2015-01-01

The purpose of this report is to emphasize the importance of maintaining capabilities for nuclear research and education, especially with regard to safety aspects, so that nuclear safety may be maintained in IAEA Member States, and to alert Member States to the potential for significant harm if the infrastructure for research, development and education is not maintained. If the infrastructure for nuclear safety is not maintained, there will be a steady decrease in expertise, and thus in capability to respond to new challenges. The lead time in developing replacement educational opportunities is very long, because most institutions will require an indication of the number of enthusiastic potential students before investing in new infrastructure, and potential students may look elsewhere in the absence of an exciting analytical and experimental programme and a growing career field. Once lost, it would require massive inputs of resources from many IAEA Member States to attempt to re-establish the infrastructure, as was done to establish it when nuclear technology was new. The result could be a downward spiral in which expertise is lost, influence of the technical community on the decision making process is diminished, and complacency, fed by diminished technical capability, begins to exert a strong effect. In view of the above, INSAG has the following recommendations: In order to maintain and further enhance the safety of nuclear facilities and to protect workers and the public and the environment from radiological consequences, the infrastructure for safety research (experimental facilities, highly competent staff and modern analytical tools) must be maintained and supported by the responsible governmental organizations as well as by the operating organizations and manufacturers. This support should include international networking and co-operation, including joint funding of centres of excellence that have facilities and equipment for use in nuclear research

International cooperation and guarantee of nuclear safety in the implementation of national nuclear law

International Nuclear Information System (INIS)

Schneider, Horst

2011-01-01

The provisions against damage to be made in accordance with the state of the art as a precondition for licensing under Sec.7, Para.2, No.3 of the German Atomic Energy Act more than ever relate to international findings and practice in science as well as technology. In view of the peaceful use of nuclear power worldwide, together with the manifold institutionalized international and European schemes for cooperation within IAEA (International Atomic Energy Agency), OECD/NEA (Organisation for Economic Cooperation and Development Nuclear Energy Agency), and within the framework of EURATOM, these can be gleaned only from the global state of the art. In addition, there are informal associations and bilateral cooperation schemes of countries within which knowledge is exchanged and, in part, even specific measures ensuring nuclear safety are agreed upon. Also existing international rules and regulations are important. It is for the national enforcement authorities in the nuclear field to determine and assess the bandwidths of scientific opinions and theoretical as well as practical technical availabilities with regard to all tenable scientific findings and technical developments known on the international horizon. (orig.)

Development of Necessary Technology for Safety Grade I and C System

International Nuclear Information System (INIS)

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

2010-08-01

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