The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

1994-01-01

The annual report on the Nordic programme for nuclear safety contains a survey of work carried out during 1993 and also the programme's budgets. Information is given on the names of project leaders, the projects' aims, methods, results and documentation. Subjects of research during 1993 have been preparedness in relation to extraordinary radiation situations, nuclear wastes and deposition of same, radioecology and reactor safety. Names of members of Nordic Nuclear Safety Research who are members of the syndicate and reference groups of the organization are listed and a note on the administration is included. (AB)

The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

Soerensen, H.C.

1993-04-01

The supplement contains a name-and-address list relevant to the Nordic Nuclear Safety Programme 1990-1993 and covering consortiums, reference groups, programme coordinators, project leaders and project participants. (AB)

The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

Soerensen, H.C.

1992-03-01

The supplement contains a name-and-address list relevant to the Nordic Nuclear Safety Programme 1990-1993 and covering consortiums, reference groups, programme coordinators, project leaders and project participants. (AB)

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)

Finnish research programmes on nuclear power plant safety

International Nuclear Information System (INIS)

Puska, E. K.

2010-01-01

The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

Programmable electronic safety systems

International Nuclear Information System (INIS)

Parry, R.R.

1993-01-01

Traditionally safety systems intended for protecting personnel from electrical and radiation hazards at particle accelerator laboratories have made extensive use of electromechanical relays. These systems have the advantage of high reliability and allow the designer to easily implement fail-safe circuits. Relay based systems are also typically simple to design, implement, and test. As systems, such as those presently under development at the Superconducting Super Collider Laboratory (SSCL), increase in size, and the number of monitored points escalates, relay based systems become cumbersome and inadequate. The move toward Programmable Electronic Safety Systems is becoming more widespread and accepted. In developing these systems there are numerous precautions the designer must be concerned with. Designing fail-safe electronic systems with predictable failure states is difficult at best. Redundancy and self-testing are prime examples of features that should be implemented to circumvent and/or detect failures. Programmable systems also require software which is yet another point of failure and a matter of great concern. Therefore the designer must be concerned with both hardware and software failures and build in the means to assure safe operation or shutdown during failures. This paper describes features that should be considered in developing safety systems and describes a system recently installed at the Accelerator Systems String Test (ASST) facility of the SSCL

The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

1992-08-01

The status report for the first half of the year 1992 of the Nordic programme for nuclear safety 1990-1993 contains summaries of the progress of the projects under the four sections of the programme. These sections are divided under the main headings of dealing with readiness in abnormal radiation situations, nuclear wastes and deposition, radioecology and reactor safety. The projects included in the first part concern radiation-spreading prognoses and consequences for the area, strategies and methods for measuring and management of exchange of data between decision-makers, evaluation and harmonizing of remedial measures, public information, Nordic exercises in readiness and the determination of radioactive contamination in the area. Projects under the second section concern exemptions from regulatory control of radioactive material, experiences of demolition of uranium cleaning systems, storing of information, handling of radioactive wastes from reactor accidents, transport etc., and geological and climatological processes of significance for long-term safety in a final storage system. The third section of the programme handles training and quality assurance methods, aquatic radioecology, agricultural and natural ecosystems. The fourth section treats data on the safety status of Greifswald I-IV, Leningrad I-IV, Ignalia I-II, ship reactors, Brunsbuettel, Kruemmel and Kola I-IV. The programme's total budget is presented. (AB)

Improvement programme of safety performance indicators (SPIs) in Korea

International Nuclear Information System (INIS)

Lee, S.Y.

2001-01-01

KINS has developed and used Safety Performance Indicators (SPIs), which are count based and composed of 10 indicators in 8 areas, to monitor the trend of performance of NPPs in Korea since 1997. However, the limited usage of SPIs and the increasing worldwide interest on SPIs became the motivation of the SPI improvement programme in Korea. Korea is planning to establish plant performance evaluation programme through analysis of SPI and result of inspection. The SPI improvement programme is a part of the plant performance evaluation programme and includes study on performance evaluation areas, indicator categories, selection and development of indicators, redefinition of indicators and introduction of graphical display system. The selected performance evaluation areas are general performance, reactor safety and radiation safety. Each area will have categories as sub-areas and a total of six categories are selected. One or two indicators for each category are determined or will be developed to make a set of Safety Performance Indicators. Also, a graphic display system will be introduced to extend the usage of SPIs. (author)

Evaluation of the Community's nuclear reactor safety research programme

International Nuclear Information System (INIS)

Brandstetter, A.; Goedkoop, J.A.; Jaumotte, A.; Malhouitre, G.; Tomkins, B.; Zorzoli, G.B.

1986-01-01

This report describes an evaluation of the 1980-85 CEC reactor safety programme prepared, at the invitation of the Commission, by a panel of six independent experts by means of examining the relevant document and by holding hearings with the responsible CEC staff. It contains the recommendations made by the panel on the following topics: the need for the JRC to continue to make its competence in the reactor safety field available to the Community; the importance of continuity in the JRC and shared-cost action programmes; the difficulty of developing reactor safety research programmes which satisfy the needs of users with diverse needs; the monitoring of the utilization of the research results; the maintenance of the JRC computer codes used by the Member States; the spin-off from research results being made available to other industrial sectors; the continued contact between the JRC researchers and the national experts; the coordination of LWR safety research with that of the Member States; and, the JRC work on fast breeders to be planned with regard to the R and D programmes of the Fast Reactor European Consortium

Presentation of the Nirex disposal safety research programme

International Nuclear Information System (INIS)

1988-01-01

Implementation of Nirex plans for the disposal of solid low and intermediate level radioactive waste deep underground requires assurances of safety at every stage. This includes assessment of long-term safety, which must be based on an understanding of how the repository and its contents will behave far into the future. This understanding is being provided by the company's substantial disposal research and development programme, currently running at a level of more than Pound 5 million annually. The principal contractor for the work is the UKAEA's Harwell Laboratory, with contributions from experts in universities and industry. Information from other national and international programmes also contributes. This document supports a presentation held at the CEGB Conference Centre, Didcot Power Station, Oxfordshire on 1st November 1988 to outline the scope of the work and its objectives in the context of the Company's plans and the requirements of safety assessments. It summarises the results and understanding being obtained from the current programme. (author)

The Nordic Nuclear Safety Research (NKS) programme. Nordic cooperation on nuclear safety

Energy Technology Data Exchange (ETDEWEB)

Andersson, Kasper G. [Technical Univ. of Denmark, Roskilde (Denmark). National Lab. for Sustainable Energy; Ekstroem, Karoliina [Fortum Power and Heat, Fortum (Finland); Gwynn, Justin P. [Norwegian Radiation Protection Authority, Tromsoe (Norway). Fram Centre; Magnusson, Sigurdur M. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Physant, Finn C. [NKS-Sekretariatet, Roskilde (Denmark)

2012-07-01

The roots of the current Nordic Nuclear Safety Research (NKS) programme can be traced back to the recommendation by the Nordic Council in the late 1950s for the establishment of joint Nordic committees on the issues of nuclear research and radiation protection. One of these joint Nordic committees, the 'Kontaktorgan', paved the way over its 33 years of existence for the future of Nordic cooperation in the field of nuclear safety, through the formation of Nordic groups on reactor safety, nuclear waste and environmental effects of nuclear power in the late 1960s and early 1970s. With an increased focus on developing nuclear power in the wake of the energy crisis on the 1970s, the NKS was established by the Nordic Council to further develop the previous strands of Nordic cooperation in nuclear safety. NKS started its first programme in 1977, funding a series of four year programmes over the next 24 years covering the areas of reactor safety, waste management, emergency preparedness and radioecology. Initially funded directly from the Nordic Council, ownership of NKS was transferred from the political level to the national competent authorities at the beginning of the 1990s. This organizational and funding model has continued to the present day with additional financial support from a number of co-sponsors in Finland, Norway and Sweden. (orig.)

Five road safety education programmes for young adolescent pedestrians and cyclists: a multi-programme evaluation in a field setting.

Science.gov (United States)

Twisk, Divera A M; Vlakveld, Willem P; Commandeur, Jacques J F; Shope, Jean T; Kok, Gerjo

2014-05-01

A practical approach was developed to assess and compare the effects of five short road safety education (RSE) programmes for young adolescents that does not rely on injury or crash data but uses self reported behaviour. Questionnaires were administered just before and about one month after participation in the RSE programmes, both to youngsters who had participated in a RSE programme, the intervention group, and to a comparable reference group of youngsters who had not, the reference group. For each RSE programme, the answers to the questionnaires in the pre- and post-test were checked for internal consistency and then condensed into a single safety score using categorical principal components analysis. Next, an analysis of covariance was performed on the obtained safety scores in order to compare the post-test scores of the intervention and reference groups, corrected for their corresponding pre-test scores. It was found that three out of five RSE programmes resulted in significantly improved self-reported safety behaviour. However, the proportions of participants that changed their behaviour relative to the reference group were small, ranging from 3% to 20%. Comparisons among programme types showed cognitive approaches not to differ in effect from programmes that used fear-appeal approaches. The method used provides a useful tool to assess and compare the effects of different education programmes on self-reported behaviour. Copyright © 2014 Elsevier Ltd. All rights reserved.

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)

The Nordic programme for nuclear safety 1990 - 1993

International Nuclear Information System (INIS)

1993-08-01

The report contains summaries written by leaders of the various projects carried out under the Nordic programme for nuclear safety during the first half-year of 1993. The programme covers spreading prognoses and consequences, strategy and methods for management and exchange of data for decision-makers, the evaluation and harmonizing of countermeasures and use of intervention levels, the basis for public information, Nordic emergency exercises, the re-establishment of radioactive contaminated areas, criteria for classification of radioactive materials, decommissioning of uranium-cleaning plants, storage of information, removal and disposal of contaminated soil from fields, influence of climatological and geological processes on longterm storage of radioactive wastes, training, quality assurance, aquatic radioecology, agriculture's radioecology, natural and semi-natural terrestrial ecosystems, reactor safety and personnel preparedness, safety evaluation, severe accidents and design and safety features of nuclear installations in countries which are neighbours to the Nordic lands. Budgets of expenditures for the various project groups are presented. (AB)

IAEA education and training programme in nuclear safety

International Nuclear Information System (INIS)

Bastos, J.L.F.; Lederman, L.

2003-01-01

This paper presents the IAEA education and training (E and T) programme in nuclear safety. A strategic planning for the programme implementation is described in terms of objectives, outputs and activities. A framework based on areas of competency and the level of depth of the training is presented as well as the main achievements to date. (author)

Design lessons from using programmable controllers in the MFTF-B personnel safety and interlocks system

International Nuclear Information System (INIS)

Branum, J.D.

1983-01-01

Applying programmable controllers in critical applications such as personnel safety and interlocks systems requires special considerations in the design of both hardware and software. All modern programmable controller systems feature extensive internal diagnostic capabilities to protect against problems such as program memory errors; however most, if not all present designs lack an intrinsic capability for detecting and countering failures on the field-side of their I/O modules. Many of the most common styles of I/O modules can also introduce potentially dangerous sneak circuits, even without component failure. This paper presents the most significant lessons learned to date in the design of the MFTF-B Personnel Safety and Interlocks System, which utilizes two non-redundant programmable controllers with over 800 I/O points each. Specific problems recognized during the design process as well as those discovered during initial testing and operation are discussed along with their specific solutions in hardware and software

Meeting Teacher Expectations in a DL Professional Development Programme--A Case Study for Sustained Applied Competence as Programme Outcome

Science.gov (United States)

Kruger, Cornè Gerda; Van Rensburg, Ona Janse; De Witt, Marike W.

2016-01-01

Meeting teacher expectations for a professional development programme (PDP) is expected to strengthen sustainable applied competence as programme outcome since teachers will be more motivated to apply the programme content in practice. A revised distance learning (DL) programme was augmented by a practical component comprising a work-integrated…

Nirex Safety Assessment Research Programme bibliography, 1990

International Nuclear Information System (INIS)

Cooper, M.J.

1990-10-01

This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. (author)

The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

1992-02-01

The report, covering the year 1991 of the Nordic Programme for Nuclear Safety 1990-1993, presents 18 projects divided into 4 main areas: preparedness in abnormal radiation situations, nuclear wastes and shutdowns, radioecology and reactor safety - knowledge preparedness. The main areas are briefly described and the status of each project is presented. (CLS) (118 refs.)

The Nirex safety assessment research programme for 1987/88

International Nuclear Information System (INIS)

Cooper, M.J.; Tasker, P.W.

1987-10-01

This report outlines the work of the Nirex Safety Assessment Research Programme during the period 1st April 1987 to 31st March 1988. The research programme has the specific objective of providing the information requirements of the post-emplacement radiological safety case for the disposal of low-level and intermediate-level radioactive waste in underground repositories. For convenience the programme has been divided into seven areas: physical containment, near-field radionuclide chemistry, evolution of the near-field aqueous environment, mass transfer in the geosphere, the biosphere, gas evolution and migration, and integrated studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the container is emplaced and the immediately adjacent geological formation disturbed by the construction of the repository. (author)

Non-animal approaches for consumer safety risk assessments: Unilever's scientific research programme.

Science.gov (United States)

Carmichael, Paul; Davies, Michael; Dent, Matt; Fentem, Julia; Fletcher, Samantha; Gilmour, Nicola; MacKay, Cameron; Maxwell, Gavin; Merolla, Leona; Pease, Camilla; Reynolds, Fiona; Westmoreland, Carl

2009-12-01

Non-animal based approaches to risk assessment are now routinely used for assuring consumer safety for some endpoints (such as skin irritation) following considerable investment in developing and applying new methods over the past 20 years. Unilever's research programme into non-animal approaches for safety assessment is currently focused on the application of new technologies to risk assessments in the areas of skin allergy, cancer and general toxicity (including inhalation toxicity). In all of these areas, a long-term investment is essential to increase the scientific understanding of the underlying biological and chemical processes that we believe will ultimately form a sound basis for novel risk assessment approaches. Our research programme in these priority areas consists of in-house research as well as Unilever-sponsored academic research, involvement with EU-funded projects (e.g. Sens-it-iv, carcinoGENOMICS), participation in cross-industry collaborative research (e.g. COLIPA, EPAA) and ongoing involvement with other scientific initiatives on non-animal approaches to risk assessment (e.g. UK NC3Rs, US 'Human Toxicology Project' consortium). 2009 FRAME.

The IAEA radioactive waste safety standards programme

International Nuclear Information System (INIS)

Tourtellotte, James R.

1995-01-01

The IAEA is currently reviewing more than thirty publications in its Safety Series with a view toward consolidating and organizing information pertaining to radioactive waste. the effort is entitled Radioactive Waste Safety Standards programme (RADWASS). RADWASS is a significant undertaking and may have far reaching effects on radioactive waste management both in the international nuclear community and in individual nuclear States. This is because IAEA envisions the development of a consensus on the final document. In this circumstance, the product of RADWASS may ultimately be regarded as an international norm against which future actions of Member States may be measured. This program is organized in five subjects: planning, pre-disposal, disposal, uranium and thorium waste management and decommissioning, which has four levels: safety fundamentals, safety standards, safety guides and safety practices. (author)

[How patient safety programmes can be successfully implemented - an example from Switzerland].

Science.gov (United States)

Kobler, Irene; Mascherek, Anna; Bezzola, Paula

2015-01-01

Internationally, the implementation of patient safety programmes poses a major challenge. In the first part, we will demonstrate that various measures have been found to be effective in the literature but that they often do not reach the patient because their implementation proves difficult. Difficulties arise from both the complexity of the interventions themselves and from different organisational settings in individual hospitals. The second part specifically describes the implementation of patient safety improvement programmes in Switzerland and discusses measures intended to bridge the gap between the theory and practice of implementation in Switzerland. Then, the national pilot programme to improve patient safety in surgery is presented, which was launched by the federal Swiss government and has been implemented by the patient safety foundation. Procedures, challenges and highlights in implementing the programme in Switzerland on a national level are outlined. Finally, first (preliminary) results are presented and critically discussed. Copyright © 2015. Published by Elsevier GmbH.

A new nuclear safety programme for areas adjacent to Finland

International Nuclear Information System (INIS)

Varjoranta, T.

1997-01-01

The projects aimed at improving nuclear and radiation safety in areas adjacent to Finland have been compiled into one programme. The purpose of the programme is to promote activities that minimise accident risks at nuclear power plants and that improve preparedness for situations involving a risk. Nuclear materials are also to be kept under strict control. In the last few years, nuclear and radiation safety has clearly improved in areas adjacent to Finland. But work is still needed to reduce the remaining risks. The Finnish support programme comprises two very definite functions. On one hand, the programme acts as a catalyst for projects launched by the Russians themselves or by the Western partners together, and strives to pave the way for international financing projects. On the other hand, assistance is given as direct support for certain hand-picked projects. (orig.)

Non-Destructive Techniques in the Tacis and Phare Nuclear Safety Programmes

International Nuclear Information System (INIS)

Bieth, Michel

2002-01-01

Decisions regarding the verification of design plant lifetime and potential license renewal periods involve a determination of the component and circuit condition. In Service Inspection of key reactor components becomes a crucial consideration for continued safe plant operation. The determination of the equipment properties by Non Destructive Techniques during periodic intervals is an important aspect of the assessment of fitness-for-service and safe operation of nuclear power plants The Tacis and Phare were established since 1991 by the European Union as support mechanisms through which projects could be identified and addressed satisfactorily. In Nuclear Safety, the countries mainly concerned are Russia, Ukraine, Armenia, and Kazakhstan for the Tacis programme, and Bulgaria, Czech Republic, Hungary, Slovak Republic, Lithuania, Romania and Slovenia for the Phare programme. The Tacis and Phare programs concerning the Nuclear Power Plants consist of: - On Site Assistance and Operational Safety, - Design Safety, - Regulatory Authorities, - Waste management, and are focused on reactor safety issues, contributing to the improvement in the safety of East European reactors and providing technology and safety culture transfer. The main parts of these programmes are related to the On-Site Assistance and to the Design Safety of VVER and RBMK Nuclear power plants where Non Destructive Techniques for In Service Inspection of the primary circuit components are addressed. (authors)

Road accident rates: strategies and programmes for improving road traffic safety.

Science.gov (United States)

Goniewicz, K; Goniewicz, M; Pawłowski, W; Fiedor, P

2016-08-01

Nowadays, the problem of road accident rates is one of the most important health and social policy issues concerning the countries in all continents. Each year, nearly 1.3 million people worldwide lose their life on roads, and 20-50 million sustain severe injuries, the majority of which require long-term treatment. The objective of the study was to identify the most frequent, constantly occurring causes of road accidents, as well as outline actions constituting a basis for the strategies and programmes aiming at improving traffic safety on local and global levels. Comparative analysis of literature concerning road safety was performed, confirming that although road accidents had a varied and frequently complex background, their causes have changed only to a small degree over the years. The causes include: lack of control and enforcement concerning implementation of traffic regulation (primarily driving at excessive speed, driving under the influence of alcohol, and not respecting the rights of other road users (mainly pedestrians and cyclists), lack of appropriate infrastructure and unroadworthy vehicles. The number of fatal accidents and severe injuries, resulting from road accidents, may be reduced through applying an integrated approach to safety on roads. The strategies and programmes for improving road traffic should include the following measures: reducing the risk of exposure to an accident, prevention of accidents, reduction in bodily injuries sustained in accidents, and reduction of the effects of injuries by improvement of post-accident medical care.

Challenges in strengthening radiation safety and security programme in Malaysia

International Nuclear Information System (INIS)

Noriah, M.A.

2010-01-01

This paper illustrates the Malaysian experience in implementing steps in strengthening radiation safety and security through certification of radiation safety personnel, which is dedicated to meet the current and future needs in sustainability of radiation safety and security systems. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important in implementing the radiation safety policy efficiently. Through this effort, we are able to create a basis for adequate protection of workers, the public and the environment and encourage licensees to manage radiation safety and security based on performance, and not on compliance culture, with the final objective of professing a safety culture through self regulation. This will certainly benefit an organisation with ultimate goals are to continuously strive for a healthy, accident free and environmentally sound workplace and community, while providing the technical support needed to meet the national mission. This will strengthen the radiation safety and security programme and could be used to assist in manpower development once Malaysia makes the decision to embark on a nuclear power programme. (author)

Performance Testing Methodology for Safety-Critical Programmable Logic Controller

International Nuclear Information System (INIS)

Kim, Chang Ho; Oh, Do Young; Kim, Ji Hyeon; Kim, Sung Ho; Sohn, Se Do

2009-01-01

The Programmable Logic Controller (PLC) for use in Nuclear Power Plant safety-related applications is being developed and tested first time in Korea. This safety-related PLC is being developed with requirements of regulatory guideline and industry standards for safety system. To test that the quality of the developed PLC is sufficient to be used in safety critical system, document review and various product testings were performed over the development documents for S/W, H/W, and V/V. This paper provides the performance testing methodology and its effectiveness for PLC platform conducted by KOPEC

Targeting International Food Aid Programmes: The Case of Productive Safety Net Programme in Tigray, Ethiopia

Directory of Open Access Journals (Sweden)

Hossein Azadi

2017-09-01

Full Text Available Ethiopia has experienced more than five major droughts in the past three decades, leading to high dependency on international food aids. Nevertheless, studies indicate that asset depletion has not been prevented; neither did food insecurity diminish. Since 2004/5, the Productive Safety Net Programme (PSNP has been implemented to improve food security in Tigray, Northern Ethiopia. Critics point out that the implementation of food aid programmes can have negative impacts as well as positive outcomes for local communities. Accordingly, this survey study aimed to analyse the distribution and allocation of food aids in the Productive Safety Net Programme (PSNP in Tigray. Results of 479 interviews revealed that targeting different households in the PSNP has been considerably linked to socio-demographic attributes among which age and size of family were decisive factors to receive food aids. Furthermore, older households with smaller family size received more direct support. Inequality between genders was another major finding of this study. When combined with the marital status, there was also a big difference in the percentage of married or unmarried women receiving food aids. These findings could provide fundamental information for policy intervention to correct food security programmes at household level and reduce hunger. Given that, socio-demographic factors can help to identify particular and usually different requirements, vulnerabilities and coping strategies of the members of the food aid programme, so that they can be much more addressed when an emergency happens.

Targeted road safety programmes : a promising approach in road safety. Paper presented at `the second conference on Asian road safety', Beijing, October 28-31, 1996.

NARCIS (Netherlands)

Wegman, F.C.M.

1996-01-01

This paper gives a broad overview on targeted road safety programmes, mainly based on the activities of a so-called OECD scientific expert group, whose report has been published in 1994 (see C 2845 S (IRRD 864087). Examples of targeted road safety programmes are given in some more detail of Finland,

The Nirex Safety Assessment Research Programme; annual report for 1988/89

International Nuclear Information System (INIS)

Cooper, M.J.

1989-07-01

This report summarises progress of the Nirex Safety Assessment Research Programme during 1988/89, in support of assessments of the post-emplacement radiological safety of a repository for the disposal of low-level and intermediate-level radioactive waste. During this period the assessments were concentrating on a comparative study of concepts and areas for deep emplacement of waste, in order to assist in the selection of preferred sites, and the research programme was therefore focussed on providing the data necessary for broad comparisons between different options to be made. (author)

Addressing safety issues through a joint industry programme; Traiter des problemes de securite a travers un programme industriel commun

Energy Technology Data Exchange (ETDEWEB)

Pool, G.; Williams, T.P. [BG Technology (United Kingdom); Jones, A.M. [Health and Safety Executive (United Kingdom)

2000-07-01

In an increasingly fragmented gas market, the focus for national gas safety may not rest with one major utility or gas supplier but may be spread across many companies. There will also be many new organisations in a liberalized gas industry with varying views on the needs and benefits of safety related technology development but all agree there is a need to ensure that the good safety record of gas as a domestic fuel is maintained. The number of carbon monoxide (CO) incidents is not decreasing significantly despite an increased awareness of the problem. As a consequence, a two-year joint industry programme addressing issues related to carbon monoxide has been established, co-ordinated by BG Technology and supported by gas organisations, government agencies, manufacturers and suppliers across Europe and the World. The 2-year 2 pound million programme has been constructed as twelve separate projects addressing issues such as the reporting and analysis of domestic incidents, improved service or installation practice, CO alarm reliability and information dissemination. The paper gives results and achievements of the programme, through new techniques, standards, procedures or equipment and demonstrates how the gas industry can work together to meet common safety objectives. (authors)

The Nordic programme for nuclear safety 1990-1993. Plan for 1993

International Nuclear Information System (INIS)

1993-04-01

In 1993 the fourth Nordic Nuclear Safety Research programme will be concluded with final reports on all of the eighteen projects. Each report will contain the results of the work carried out which has taken four years to complete and, at the same time, give a more general survey of the Northern countries' competence within the fields of emergency readiness in situations of abnormal radiation, radioactive waste and its disposal, radioecology and nuclear reactor safety - accessibility of appropriate information. Some of the reports will be published in the form of reference books or in the form of databases of direct assistance to the authorities. A number of seminars will be held so that the results and professional level of the reports can be discussed. The coordinators' and project leaders' plans for these activities are presented with the the amounts of money that project organizers have asked the Nordic Nuclear Safety Research programme to finance them with. During 1993 the plans for the programme starting in 1994 must be laid, and future researchers, project leaders, involved organizations and sponsors determined. (AB)

The IAEA extrabudgetary programme on the safety of WWER and RBMK plants

International Nuclear Information System (INIS)

Havel, R.

1995-01-01

Data on WWER-440/213, WWER-440/230, WWER-1000 and RBMK reactors in operation are presented. Organizational chart for the IAEA extrabudgetary programme on the safety of WWER and RBMK plants, general programme objectives and main components are outlined

IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

International Nuclear Information System (INIS)

2014-01-01

The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

International Nuclear Information System (INIS)

Puska, E.

2006-12-01

Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

Economic evaluation of occupational health and safety programmes in health care.

Science.gov (United States)

Guzman, J; Tompa, E; Koehoorn, M; de Boer, H; Macdonald, S; Alamgir, H

2015-10-01

Evidence-based resource allocation in the public health care sector requires reliable economic evaluations that are different from those needed in the commercial sector. To describe a framework for conducting economic evaluations of occupational health and safety (OHS) programmes in health care developed with sector stakeholders. To define key resources and outcomes to be considered in economic evaluations of OHS programmes and to integrate these into a comprehensive framework. Participatory action research supported by mixed qualitative and quantitative methods, including a multi-stakeholder working group, 25 key informant interviews, a 41-member Delphi panel and structured nominal group discussions. We found three resources had top priority: OHS staff time, training the workers and programme planning, promotion and evaluation. Similarly, five outcomes had top priority: number of injuries, safety climate, job satisfaction, quality of care and work days lost. The resulting framework was built around seven principles of good practice that stakeholders can use to assist them in conducting economic evaluations of OHS programmes. Use of a framework resulting from this participatory action research approach may increase the quality of economic evaluations of OHS programmes and facilitate programme comparisons for evidence-based resource allocation decisions. The principles may be applicable to other service sectors funded from general taxes and more broadly to economic evaluations of OHS programmes in general. © The Author 2015. Published by Oxford University Press on behalf of the Society of Occupational Medicine. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Collective statement on major nuclear safety research facilities and programmes at risk

International Nuclear Information System (INIS)

2001-01-01

Nuclear safety research remains necessary, since nuclear power programmes are dynamic. In addition to maintaining in-depth competencies, its aim is to provide information to plant designers, operators and regulators in support of the resolution of safety issues, to strengthen confidence in their solution and their implementation, and also to anticipate problems of potential significance. New fields of research open up as a result of plant ageing, plant life extension, plant up-rating, optimisation of plant economics and the associated need to further reduce uncertainties in safety margins quantification. The safety evaluation of future reactor systems being developed or considered in several Member countries also requires new research efforts. Accordingly, Member countries are encouraged to support efforts to maintain key research data, facilities and programmes through national support of international co-operation and funding. This should be under-pinned by development of short-, medium- and long-term strategic visions of the needs of the nuclear safety research community, including a strong component of international collaboration given the international nature of nuclear safety issues. (author)

Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-01-15

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances.

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances

Organisational readiness: exploring the preconditions for success in organisation-wide patient safety improvement programmes.

Science.gov (United States)

Burnett, Susan; Benn, Jonathan; Pinto, Anna; Parand, Anam; Iskander, Sandra; Vincent, Charles

2010-08-01

Patient safety has been high on the agenda for more than a decade. Despite many national initiatives aimed at improving patient safety, the challenge remains to find coherent and sustainable organisation-wide safety-improvement programmes. In the UK, the Safer Patients' Initiative (SPI) was established to address this challenge. Important in the success of such an endeavour is understanding 'readiness' at the organisational level, identifying the preconditions for success in this type of programme. This article reports on a case study of the four NHS organisations participating in the first phase of SPI, examining the perceptions of organisational readiness and the relationship of these factors with impact by those actively involved in the initiative. A mixed-methods design was used, involving a survey and semistructured interviews with senior executive leads, the principal SPI programme coordinator and the four operational leads in each of the SPI clinical work areas in all four organisations taking part in the first phase of SPI. This preliminary work would suggest that prior to the start of organisation-wide quality- and safety-improvement programmes, organisations would benefit from an assessment of readiness with time spent in the preparation of the organisational infrastructure, processes and culture. Furthermore, a better understanding of the preconditions that mark an organisation as ready for improvement work would allow policymakers to set realistic expectations about the outcomes of safety campaigns.

Establishment of radiation protection and safety programme in Nuclear Medicine

International Nuclear Information System (INIS)

Chene, E.

2014-04-01

Radiation is useful because of its ability to penetrate tissue, allowing imaging of internal structures. However radiation may produce harmful biological effects. Observations of exposed human populations and animal experimentation indicate that exposure to low levels of radiation over a period of time may lead to stochastic radiation effects. Exposures to high levels of radiation above threshold also leads to deterministic effects. Establishment of radiation protection and safety programme and implement it without fail may help prevent deterministic effect and limit chances of stochastic effects. This is achieved by assigning responsibilities to the proposed organizational structure, management commitment to safety culture by providing continuous education and training to employees, regular reviewing and auditing of radiation safety policies. Occupational, public and environmental radiation exposure is further achieved by implementation of set local rules and operational procedures, proper management of radioactive waste and safe transport of radioactive material. Medical radiation exposure is achieved by justified procedures, optimization of doses, guidance levels, quality assurance and quality control programme through image quality, radiopharmaceutical quality and records keeping of radiation doses, calibration certificates of equipment used, equipment service and test certificates. Diagnostic radiopharmaceuticals must deliver the minimum possible radiation dose to the patient while therapeutic radiopharmaceuticals must deliver the maximum dose to the target organ or tissue, while minimizing the dose to non-target tissues such as the bone marrow. Special considerations shall be given to pregnant and breast-feeding patients. The proper facility design and shielding of a nuclear medicine facility shall further provide for the radiation protection to the worker, the patient, public and the environment. Precautions should be given to radioactive patients as there

Applying the Ottawa Charter to inform health promotion programme design.

Science.gov (United States)

Fry, Denise; Zask, Avigdor

2017-10-01

There is evidence of a correlation between adoption of the Ottawa Charter's framework of five action areas and health promotion programme effectiveness, but the Charter's framework has not been as fully implemented as hoped, nor is generally used by formal programme design models. In response, we aimed to translate the Charter's framework into a method to inform programme design. Our resulting design process uses detailed definitions of the Charter's action areas and evidence of predicted effectiveness to prompt greater consideration and use of the Charter's framework. We piloted the process by applying it to the design of four programmes of the Healthy Children's Initiative in New South Wales, Australia; refined the criteria via consensus; and made consensus decisions on the extent to which programme designs reflected the Charter's framework. The design process has broad potential applicability to health promotion programmes; facilitating greater use of the Ottawa Charter framework, which evidence indicates can increase programme effectiveness. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Large-scale road safety programmes in low- and middle-income countries: an opportunity to generate evidence.

Science.gov (United States)

Hyder, Adnan A; Allen, Katharine A; Peters, David H; Chandran, Aruna; Bishai, David

2013-01-01

The growing burden of road traffic injuries, which kill over 1.2 million people yearly, falls mostly on low- and middle-income countries (LMICs). Despite this, evidence generation on the effectiveness of road safety interventions in LMIC settings remains scarce. This paper explores a scientific approach for evaluating road safety programmes in LMICs and introduces such a road safety multi-country initiative, the Road Safety in 10 Countries Project (RS-10). By building on existing evaluation frameworks, we develop a scientific approach for evaluating large-scale road safety programmes in LMIC settings. This also draws on '13 lessons' of large-scale programme evaluation: defining the evaluation scope; selecting study sites; maintaining objectivity; developing an impact model; utilising multiple data sources; using multiple analytic techniques; maximising external validity; ensuring an appropriate time frame; the importance of flexibility and a stepwise approach; continuous monitoring; providing feedback to implementers, policy-makers; promoting the uptake of evaluation results; and understanding evaluation costs. The use of relatively new approaches for evaluation of real-world programmes allows for the production of relevant knowledge. The RS-10 project affords an important opportunity to scientifically test these approaches for a real-world, large-scale road safety evaluation and generate new knowledge for the field of road safety.

The waste isolation safety assessment programme

International Nuclear Information System (INIS)

Brandstetter, A.; Harwell, M.A.

1980-01-01

Associated with commercial nuclear power production in the USA is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE), through the National Waste Terminal Storage (NWTS) Programme, is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Programme (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Among the analyses required for isolation system evaluation is the detailed assessment of the post-closure performance of nuclear waste repositories in geologic formations. This assessment is essential, since it is concerned with aspects of the nuclear power programme which previously have not been addressed. Specifically, the nature of the isolation systems (e.g. involving breach scenarios and transport through the geosphere), and the time-scales necessary for isolation, dictate the development, demonstration and application of novel assessment capabilities. The assessment methodology needs to be thorough, flexible, objective, and scientifically defensible. Further, the data utilized must be accurate, documented, reproducible, and based on sound scientific principles. (author)

Annual report 1999. NKS-programme 1998-2001[Nordic Nuclear Safety Programme]; Aarsrapport 1999. NKS-programmet 1998-2001

Energy Technology Data Exchange (ETDEWEB)

Bennerstedt, T. [ed.

2000-02-01

The Nordic nuclear safety programme consists of projects within the areas of risk assessment, reactor safety, waste, emergency preparedness, and environmental consequences. The annual report presents results and economic issues in relation to approved project plans and budgets. Also the more important reports, agreements, seminars, meetings etc are listed. Participating organisations and persons are mentioned, and the total national contributions (besides NKS- own means) to research are stated. (EHS)

The Safety Assessment Education and Training Programme (SAET). Education and Training in the Area of Safety Assessment

International Nuclear Information System (INIS)

Mellinger-Deroy, M.

2014-01-01

• The SAET Programme provides a systematic approach for training regulatory, operational and technical support staff in the skills needed for informed decision-making and technical review of NPP safety case documentation. • The objective of the Programme is to support the IAEA Member States in developing the knowledge and skills necessary for making the right decisions in NPP design, licensing and operation. (author)

Development and perceived effects of an educational programme on quality and safety in medication handling in residential facilities.

Science.gov (United States)

Mygind, Anna; El-Souri, Mira; Rossing, Charlotte; Thomsen, Linda Aagaard

2018-04-01

To develop and test an educational programme on quality and safety in medication handling for staff in residential facilities for the disabled. The continuing pharmacy education instructional design model was used to develop the programme with 22 learning objectives on disease and medicines, quality and safety, communication and coordination. The programme was a flexible, modular seven + two days' course addressing quality and safety in medication handling, disease and medicines, and medication supervision and reconciliation. The programme was tested in five Danish municipalities. Municipalities were selected based on their application for participation; each independently selected a facility for residents with mental and intellectual disabilities, and a facility for residents with severe mental illnesses. Perceived effects were measured based on a questionnaire completed by participants before and after the programme. Effects on motivation and confidence as well as perceived effects on knowledge, skills and competences related to medication handling, patient empowerment, communication, role clarification and safety culture were analysed conducting bivariate, stratified analyses and test for independence. Of the 114 participants completing the programme, 75 participants returned both questionnaires (response rate = 66%). Motivation and confidence regarding quality and safety in medication handling significantly improved, as did perceived knowledge, skills and competences on 20 learning objectives on role clarification, safety culture, medication handling, patient empowerment and communication. The programme improved staffs' motivation and confidence and their perceived ability to handle residents' medication safely through improved role clarification, safety culture, medication handling and patient empowerment and communication skills. © 2017 Royal Pharmaceutical Society.

Statistical analysis applied to safety culture self-assessment

International Nuclear Information System (INIS)

Macedo Soares, P.P.

2002-01-01

Interviews and opinion surveys are instruments used to assess the safety culture in an organization as part of the Safety Culture Enhancement Programme. Specific statistical tools are used to analyse the survey results. This paper presents an example of an opinion survey with the corresponding application of the statistical analysis and the conclusions obtained. Survey validation, Frequency statistics, Kolmogorov-Smirnov non-parametric test, Student (T-test) and ANOVA means comparison tests and LSD post-hoc multiple comparison test, are discussed. (author)

Integration of Behaviour-Based Safety Programme into Engineering Laboratories and Workshops Conceptually

Science.gov (United States)

Koo, Kean Eng; Zain, Ahmad Nurulazam Md; Zainal, Siti Rohaida Mohamed

2012-01-01

The purpose of this conceptual research framework is to develop and integrate a safety training model using a behaviour-based safety training programme into laboratories for young adults, during their tertiary education, particularly in technical and vocational education. Hence, this research will be investigating the outcome of basic safety…

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

Energy Technology Data Exchange (ETDEWEB)

Simola, K. [ed.

2013-02-15

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

International Nuclear Information System (INIS)

Simola, K.

2013-02-01

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

Report of a consultants` meeting to review the IAEA programme on operational safety services as part of the programme performance assessment system (PPAS) within the IAEA

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

The consultants consider that the ASCOT (Assessment of Safety Culture in Organizations Team), ASSET (Assessment of Safety Significant Events Team), and OSART (Operational Safety Review Team) programmes contribute to enhancing safe performance of Member States nuclear power plants. Continued co-ordination with the World Association of Nuclear Operators and national programmes in addition to continued emphasis on developing self assessment capabilities at the power plants will contribute to continuing improvement. International performance indicators clearly portray improvements in almost all areas. For example, the incidence of unplanned scrams and the unavailability of systems important to safety reduced. All three programmes ASCOT, ASSET and OSART may be improved by: tailoring them to meet the requested need. This includes not only the use of the OSART modular concepts but also the mixing and matching of the programmes. All three programmes can be enhanced by the sharing and use of their individual current techniques. The balance between assistance for conducting self assessment and direct assessment activities must be carefully considered. Country profiles could assist the Agency staff in advising Member States on request in the technique; power plant assistance or direct assessment, that would yield the best result. It is therefore recommended that the Agency go forward with the effort to develop these profiles. Figs, tabs.

Report of a consultants' meeting to review the IAEA programme on operational safety services as part of the programme performance assessment system (PPAS) within the IAEA

International Nuclear Information System (INIS)

1996-09-01

The consultants consider that the ASCOT (Assessment of Safety Culture in Organizations Team), ASSET (Assessment of Safety Significant Events Team), and OSART (Operational Safety Review Team) programmes contribute to enhancing safe performance of Member States nuclear power plants. Continued co-ordination with the World Association of Nuclear Operators and national programmes in addition to continued emphasis on developing self assessment capabilities at the power plants will contribute to continuing improvement. International performance indicators clearly portray improvements in almost all areas. For example, the incidence of unplanned scrams and the unavailability of systems important to safety reduced. All three programmes ASCOT, ASSET and OSART may be improved by: tailoring them to meet the requested need. This includes not only the use of the OSART modular concepts but also the mixing and matching of the programmes. All three programmes can be enhanced by the sharing and use of their individual current techniques. The balance between assistance for conducting self assessment and direct assessment activities must be carefully considered. Country profiles could assist the Agency staff in advising Member States on request in the technique; power plant assistance or direct assessment, that would yield the best result. It is therefore recommended that the Agency go forward with the effort to develop these profiles. Figs, tabs

ASAM - The international programme on application of safety assessment methodologies for near surface radioactive waste disposal facilities

International Nuclear Information System (INIS)

Batandjieva, B.

2002-01-01

The IAEA has launched a new Co-ordinated Research Project (CRP) on Application of Safety Assessment Methodologies for Near Surface Waste Disposal Facilities (ASAM). The CRP will focus on the practical application of the safety assessment methodology, developed under the ISAM programme, for different purposes, such as developing design concepts, licensing, upgrading existing repositories, reassessment of operating disposal facilities. The overall aim of the programme is to assist safety assessors, regulators and other specialists involved in the development and review of safety assessment for near surface disposal facilities in order to achieve transparent, traceable and defendable evaluation of safety of these facilities. (author)

Britain's Nuclear Electric pursues a major programme to enhance safety

International Nuclear Information System (INIS)

Anon.

1991-01-01

The UK state-owned nuclear utility, Nuclear Electric, is actively pursuing a major initiative inherited from its predecessor the Central Electricity Generating Board, known as the Station Enhancement Programme. The Enhancement Programme is a multi-million pound project and covers all Nuclear Electric's stations (including relevant aspects of the de-commissioning site at Berkeley). Its fundamental objective is to enhance the arrangements, practices and attitudes on the power stations to create an overall environment likely to promote ever safer and more reliable operation, and to take full account of the best international practices. The four year programme started in the spring of 1989, and is expected to be completed in 1993. Key elements of the programme include quality assurance based management systems; improvements to site and plant material conditions; a more formal approach to training; additional resources and controls to aid the management of maintenance defects; higher profile for the feedback of operational experience; management targets; a station evaluation programme; and formal feedback of lessons learned from the IAEA operational and safety review team visit to the Oldbury-on-Severn station in 1989. (author)

RETU. The Finnish research programme on reactor safety. Interim report 1995 - May 1997

International Nuclear Information System (INIS)

Vanttola, T.; Puska, E.K.

1997-08-01

The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 - May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched

RETU. The Finnish research programme on reactor safety. Interim report 1995 - May 1997

Energy Technology Data Exchange (ETDEWEB)

Vanttola, T; Puska, E K [VTT Energy, Espoo (Finland). Nuclear Energy; eds.

1997-08-01

The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 - May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. 135 refs.

RETU The Finnish research programme on reactor safety 1995-1998. Final Symposium

International Nuclear Information System (INIS)

Vanttola, T.

1998-01-01

The Reactor Safety (RETU, 1995-1998) research programme concentrated on search of safe limits for nuclear fuel and the reactor core, accident management methods and risk management of nuclear power plants. The total volume of the programme was 100 person years and funding FIM 58 million. This symposium report summarises the research fields, the objectives and the main results obtained. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel was studied both in normal operation and during power transients. The static and dynamic reactor analysis codes were developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients. Advanced flow models and numerical solution methods for the dynamics codes were developed and tested. Research on accident management developed and validated calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Efforts were made to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme included experimental work, but also participation in large international tests. The Finnish thermal-hydraulic test facility PACTEL was used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In risk management probabilistic methods were developed for safety related decision making and for complex event sequences. Effects of maintenance on safety were studied and effective methods for assessment of human reliability and safety critical organisations were searched. To enhance human competencies in control of complex environments, practical tools for training and continuous learning were worked out, and methods to evaluate appropriateness of control room design were developed. (orig)

Radiation and nuclear safety included in the environmental health programme

International Nuclear Information System (INIS)

Salomaa, S.

1996-01-01

Finland is currently preparing a national environmental health programme, the objective of which is to chart the main environmental health problems in Finland, to identify means for securing a healthy environment, and to draw up a practical action programme for preventing and rectifying problems pertaining to environmental health. Radiation and nuclear safety form an essential part of preventive health care. The action programme is based on decisions and programmes approved at the WHO Conference on the Environment and Health, held in Helsinki in June 1994. In addition to the state of the Finnish environment and the health of the Finnish population, the programme addresses the relevant international issues, in particular in areas adjacent to Finland. The Committee on Environmental Health is expected to complete its work by the end of the year. A wide range of representatives from various branches of administration have contributed to the preparation of the programme. Besides physical, biological and chemical factors, the environmental factors affecting health also include the physical environment and the psychological, social and aesthetic features of the environment. Similarly, environmental factors that have an impact on the health of present or future generations, on the essential preconditions of life and on the quality of life are investigated. The serious risk to nature caused by human actions is also considered as a potential risk to human health. (orig.)

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances

Applying a realistic evaluation model to occupational safety interventions

DEFF Research Database (Denmark)

Pedersen, Louise Møller

2018-01-01

Background: Recent literature characterizes occupational safety interventions as complex social activities, applied in complex and dynamic social systems. Hence, the actual outcomes of an intervention will vary, depending on the intervention, the implementation process, context, personal characte......Background: Recent literature characterizes occupational safety interventions as complex social activities, applied in complex and dynamic social systems. Hence, the actual outcomes of an intervention will vary, depending on the intervention, the implementation process, context, personal...... and qualitative methods. This revised model has, however, not been applied in a real life context. Method: The model is applied in a controlled, four-component, integrated behaviour-based and safety culture-based safety intervention study (2008-2010) in a medium-sized wood manufacturing company. The interventions...... involve the company’s safety committee, safety manager, safety groups and 130 workers. Results: The model provides a framework for more valid evidence of what works within injury prevention. Affective commitment and role behaviour among key actors are identified as crucial for the implementation...

New and recently finalised activities within the NKS Programmes for Nordic cooperation on nuclear reactor safety and emergency preparedness

DEFF Research Database (Denmark)

Andgren, Karin; Andersson, Kasper Grann; Magnússon, Sigurður M.

2015-01-01

Over the years, NKS has provided funding for hundreds of research activities in fields comprising reactor safety, decommissioning, nuclear and radiological emergency preparedness, and management of radioactive waste. Advanced technologies and methods developed under the NKS framework have been used...... within the Nordic countries as well as internationally. Two programme areas are defined under the NKS platform: The NKS-R programme on nuclear reactor safety and the NKS-B programme on emergency preparedness. Three articles, giving an introduction to NKS and its two programmes, were published...

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

International Nuclear Information System (INIS)

2009-06-01

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

radiation safety culture for developing country: Basis for s minimum operational radiation protection programme

International Nuclear Information System (INIS)

Rozental, J. J.

1997-01-01

The purpose of this document is to present a methodology for an integrated strategy aiming at establishing an adequate radiation Safety infrastructure for developing countries, non major power reactor programme. Its implementation will allow these countries, about 50% of the IAEA's Member States, to improve marginal radiation safety, specially to those recipients of technical assistance and do not meet the Minimum radiation Safety Requirements of the IAEA's Basic Safety Standards for radiation protection Progress in the implementation of safety regulations depends on the priority of the government and its understanding and conviction about the basic requirements for protection against the risks associated with exposure to ionizing radiation. There is no doubt to conclude that the reasons for the deficiency of sources control and dose limitation are related to the lack of an appropriate legal and regulatory framework, specially considering the establishment of an adequate legislation; A minimum legal infrastructure; A minimum operational radiation safety programme; Alternatives for a Point of Optimum Contact, to avoid overlap and conflict, that is: A 'Memorandum of Understanding' among Regulatory Authorities in the Country, dealing with similar type of licensing and inspection

The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

1991-08-01

The status report concerning the Nordic Nuclear Safety Programme for 1990-1993 contains a summary of the current situation regarding research projects, presented by the four coordinators, and a survey of the related economy. It is stated that all seventeen projects are running satisfactorily and a number of working descriptions have been published. Project leaders work with contracts with consultant firms, research organizations and individuals, contact meetings including lectures and discussions, mini-seminars where participants actually work at the same time, coordination of nationally financed research projects and individual contributions. Problems related to a certain lack of qualified persons for whom it is possible to coordinate this Nordic work with their daily responsibilities have led to delays in relation to the working plans and this has resulted in the fact that not all the grants have been utilized as yet. Sub-programmes are dealt with individually, and lists of publications are presented. (AB) (10 refs.)

From aviation to medicine: applying concepts of aviation safety to risk management in ambulatory care.

Science.gov (United States)

Wilf-Miron, R; Lewenhoff, I; Benyamini, Z; Aviram, A

2003-02-01

The development of a medical risk management programme based on the aviation safety approach and its implementation in a large ambulatory healthcare organisation is described. The following key safety principles were applied: (1). errors inevitably occur and usually derive from faulty system design, not from negligence; (2). accident prevention should be an ongoing process based on open and full reporting; (3). major accidents are only the "tip of the iceberg" of processes that indicate possibilities for organisational learning. Reporting physicians were granted immunity, which encouraged open reporting of errors. A telephone "hotline" served the medical staff for direct reporting and receipt of emotional support and medical guidance. Any adverse event which had learning potential was debriefed, while focusing on the human cause of error within a systemic context. Specific recommendations were formulated to rectify processes conducive to error when failures were identified. During the first 5 years of implementation, the aviation safety concept and tools were successfully adapted to ambulatory care, fostering a culture of greater concern for patient safety through risk management while providing support to the medical staff.

Safety assessments using surveillance programmes and data base

International Nuclear Information System (INIS)

Njo, D.H.

1998-01-01

As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. Chapter 12 presents some aspects on safety assessments of RPV materials during the life of a NPP, using surveillance programmes and data bases. Specific criteria for the usefulness of data bases are developed

Five road safety education programmes for young adolescent pedestrians and cyclists : A multi-programme evaluation in a field setting

NARCIS (Netherlands)

Twisk, Divera A.M.; Vlakveld, Willem P.; Commandeur, Jacques J.F.; Shope, Jean T.; Kok, Gerjo

A practical approach was developed to assess and compare the effects of five short road safety education (RSE) programmes for young adolescents that does not rely on injury or crash data but uses self reported behaviour. Questionnaires were administered just before and about one month after

Five road safety education programmes for young adolescent pedestrians and cyclists : a multi-programme evaluation in a field setting.

NARCIS (Netherlands)

Twisk, D.A.M. Vlakveld, W.P. Commandeur, J.J.F. Shope, J.T. & Kok, G.

2014-01-01

A practical approach was developed to assess and compare the effects of five short road safety education (RSE) programmes for young adolescents that does not rely on injury or crash data but uses self reported behaviour. Questionnaires were administered just before and about one month after

Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

Programmable controllers replace relays in MFTF-B personnel-safety interlocks

International Nuclear Information System (INIS)

Branum, J.D.

1981-01-01

This paper describes a new approach for implementing personnel safety interlocks logic using industrial-type programmable controllers. The logic for all personnel safety interlocks except those totally internal to a subsystem is implemented in two non-redundant controllers. A high degree of fail-safe reliability is achieved by augmenting the protective features intrinsic to each controller with those provided by a small amount of external support hardware. The controllers are interfaced to the host computer system via fiber optic data links to enable display of interlock and overall system status on the control room graphic displays. When fully implemented, the controllers will perform the equivalent of over 2000 discreet relay functions

Applying principles from safety science to improve child protection.

Science.gov (United States)

Cull, Michael J; Rzepnicki, Tina L; O'Day, Kathryn; Epstein, Richard A

2013-01-01

Child Protective Services Agencies (CPSAs) share many characteristics with other organizations operating in high-risk, high-profile industries. Over the past 50 years, industries as diverse as aviation, nuclear power, and healthcare have applied principles from safety science to improve practice. The current paper describes the rationale, characteristics, and challenges of applying concepts from the safety culture literature to CPSAs. Preliminary efforts to apply key principles aimed at improving child safety and well-being in two states are also presented.

The dynamic flowgraph methodology as a safety analysis tool : programmable electronic system design and verification

NARCIS (Netherlands)

Houtermans, M.J.M.; Apostolakis, G.E.; Brombacher, A.C.; Karydas, D.M.

2002-01-01

The objective of this paper is to demonstrate the use of the Dynamic Flowgraph Methodology (DFM) during the design and verification of programmable electronic safety-related systems. The safety system consists of hardware as well as software. This paper explains and demonstrates the use of DFM, and

The Nirex safety assessment research programme: annual report for 1985/86

International Nuclear Information System (INIS)

Hodgkinson, D.P.; Cooper, M.J.; Atkinson, A.

1987-01-01

The report describes progress of the Nirex Safety Assessment Research Programme in 1985/86. In addition, some background information is given on the overall programme and on the individual research projects, and likely future work is outlined. Research into the disposal of low-level waste (LLW) and intermediate-level waste (ILW) into underground repositories and onto the sea bed is reported. A large part of the programme is concerned with the effectiveness of near-field barriers to water-borne leakage of radionuclides from cementitious repositories. Considerable progress has been made with quantifying the longevity of steel containers and concrete structures, and the effectiveness of chemical constraints in limiting near-field concentrations. A range of techniques for measuring and modelling far-field phenomena has been developed and tested. Some initial studies have been performed to assess the durability of sea disposal packages and the behaviour of polythene in sea water. (author)

National Nuclear Power Plant Safety Research 2003-2006. Proposal for the Content and Organisation of a New Research Programme

International Nuclear Information System (INIS)

2002-11-01

A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating and supervisory organisations of the plants. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. The Steering Group to the Finnish Research Programme on Nuclear Power Plant Safety (FINNUS), which was launched upon the assignment of the Advisory Committee on Nuclear Energy, appointed in spring 2002 a group to plan the contents of the new programme. This report contains a proposal for the general outline of the programme, preliminarily entitled as SAFIR (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2003-2006, but it is based on safety challenges identified for a longer time span as well. The favourable decision-in-principle on a new nuclear power plant unit adopted by Parliament has also been taken into account in the plan. The safety challenges set by the existing plants and the new plant unit, as well as the ensuing research needs do, however, converge to a great extent. The construction of the new power plant unit will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The general plan aims to define the

From aviation to medicine: applying concepts of aviation safety to risk management in ambulatory care

Science.gov (United States)

Wilf-Miron, R; Lewenhoff, I; Benyamini, Z; Aviram, A

2003-01-01



 The development of a medical risk management programme based on the aviation safety approach and its implementation in a large ambulatory healthcare organisation is described. The following key safety principles were applied: (1) errors inevitably occur and usually derive from faulty system design, not from negligence; (2) accident prevention should be an ongoing process based on open and full reporting; (3) major accidents are only the "tip of the iceberg" of processes that indicate possibilities for organisational learning. Reporting physicians were granted immunity, which encouraged open reporting of errors. A telephone "hotline" served the medical staff for direct reporting and receipt of emotional support and medical guidance. Any adverse event which had learning potential was debriefed, while focusing on the human cause of error within a systemic context. Specific recommendations were formulated to rectify processes conducive to error when failures were identified. During the first 5 years of implementation, the aviation safety concept and tools were successfully adapted to ambulatory care, fostering a culture of greater concern for patient safety through risk management while providing support to the medical staff. PMID:12571343

Assessing the Food Safety Attitudes and Awareness of Managers of School Feeding Programmes in Mpumalanga, South Africa.

Science.gov (United States)

Sibanyoni, J J; Tabit, F T

2017-08-01

The managers of school feeding programmes are responsible for ensuring the safety of the food which is provided to schoolchildren, but very few studies have been conducted on the food safety knowledge and awareness of these managers. The objective of this study is to evaluate the food safety attitudes and awareness of managers of the National School Nutrition Programme (NSNP) in schools in Mpumalanga, a province of South Africa. A cross-sectional survey study was conducted in which questionnaires were used to collect data from 300 NSNP food service managers. The majority of schools offering NSNP meals were located in informal settlements and most were found to lack basic resources such as electricity (power supplies to the food preparation facility) and potable tap water in their kitchens. No school was found to have implemented the hazard analysis and critical control points (HACCP) programme, and only a few staff had received food safety training. Food safety implementation is worst in informal schools in rural areas due to limited resources and infrastructure. The NSNP food service managers in some schools-especially those located in rural settlements-were found to have little knowledge and awareness of HACCP. These results indicate an urgent need to provide NSNP managers with food safety training and resources (potable water supplies, electricity, dedicated food preparation facilities), particularly in schools in rural settlements.

Multinational Design Evaluation Programme (MDEP) - Safety Goals

International Nuclear Information System (INIS)

Vaughan, G.J.

2011-01-01

One of the aims of the NEA's Multinational Design Evaluation Programme (MDEP) is to work towards greater harmonisation of regulatory requirements. To achieve this aim, it is necessary that there is a degree of convergence on the safety goals that are required to be met by designers and operators. The term 'safety goals' is defined to cover all health and safety requirements which must be met: these may be deterministic rules and/or probabilistic targets. They should cover the safety of workers, public and the environment in line with the IAEA's Basic Safety Objective; encompassing safety in normal operation through to severe accidents. MDEP is also interested in how its work can be extended to future reactors, which may use significantly different technology to the almost ubiquitous LWRs used today and in the next generation, building on the close co-operation within MDEP between the regulators who are currently engaged in constructing or carrying out design reviews on new designs. For two designs this work has involved several regulators sharing their safety assessments and in some cases issuing statements on issues that need to be addressed. Work is also progressing towards joint regulatory position statements on specific assessment areas. Harmonisation of safety goals will enhance the cooperation between regulators as further developments in design and technology occur. All regulators have safety goals, but these are expressed in many different ways and exercises in comparing them frequently are done at a very low level eg specific temperatures in the reactor vessel of a specific reactor type. The differences in the requirements from different regulators are difficult to resolve as the goals are derived using different principles and assumptions and are often for a specific technology. Therefore a different approach is being investigated, starting with the top-level safety goals and try to derive a structure and means of deriving lower tier

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

YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety

International Nuclear Information System (INIS)

Mattila, L.; Vanttola, T.

1992-01-01

The major part of nuclear energy research in Finland has been organised as five-year nationally coordinated research programs. The research programme on Systems Behaviour and Operational Aspects of Safety is under way during 1990-1994. Its annual volume has been about 35 person-years and its annual expenditure about FIM 18 million. Studies in the field on safe operational margins of nuclear fuel and reactor core concentrate on fuel high burn-up behaviour, VVER fuel experiments, and reactor core behaviour in complex reactivity transients such as 3-D phenomena and ATWS events. The PACTEL facility is used for the thermal hydraulic studies of the Loviisa type reactors (scaled 1:305). Validation of accident analysis codes is carried out by participation in international standard problems. Advanced foreign computer codes for severe reactor accidents are implemented, modified as needed and applied to level-2 PSAs and the improvement of accident management procedures. Fire simulation methods are tested using data from experiments in the German HDR facility. A nuclear plant analyzer for efficient safety analyses is being developed using the APROS process simulation environment. Computerized operator support systems are being studied in cooperation with the OECD Halden Project. The basic factors affecting plant operator activities and the development of their competence are being investigated. A comprehensive system for the control of plant operational safety is being developed by combining living PSA and safety indicators

Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010)

International Nuclear Information System (INIS)

2015-12-01

Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on the CD-ROM which accompanies this report

Radiation protection programmes for the transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2007-01-01

This Safety Guide provides guidance on meeting the requirements for the establishment of radiation protection programmes (RPPs) for the transport of radioactive material, to optimize radiation protection in order to meet the requirements for radiation protection that underlie the Regulations for the Safe Transport of Radioactive Material. This Guide covers general aspects of meeting the requirements for radiation protection, but does not cover criticality safety or other possible hazardous properties of radioactive material. The annexes of this Guide include examples of RPPs, relevant excerpts from the Transport Regulations, examples of total dose per transport index handled, a checklist for road transport, specific segregation distances and emergency instructions for vehicle operators

The Safety Tips for ATV Riders (STARs) programme: short-term impact of a school-based educational intervention.

Science.gov (United States)

Jennissen, Charles A; Peck, Jeffrey; Wetjen, Kristel; Hoogerwerf, Pam; Harland, Karisa K; Denning, Gerene M

2015-06-01

Since 1985, one-third of all US all-terrain vehicle (ATV)-related injuries and one-quarter of deaths involved victims safety education of youth could help reduce these tragedies. To assess the efficacy of the Safety Tips for ATV Riders (STARs) school-based programme targeting adolescents. A survey was anonymously administered before and after the programme to determine demographics, knowledge and reported likelihood of using the information learned. Over 4600 students in 30 Iowa schools participated from November 2010 to April 2013. Initially, 52% knew most ATVs are designed for one rider, 25% knew the recommended vehicle size for their age range and 42% knew riding on Iowa's roads was legal only for agricultural purposes. After the programme, this increased to 92%, 82% and 76%, respectively (psafety information learned, respectively; younger students, females and infrequent riders reported higher likelihoods. STARs increased short-term ATV safety knowledge and almost half the participants reported they would use the safety information presented. Males and frequent riders seemed more resistant, but some groups that may be more vulnerable to potential ATV crash and injury appeared amenable to the training with higher increases in postprogramme scores and greater intention of improving safety behaviours. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

Evaluation of the safety research programme 1985-1989 by the Nordic Liaison Committee for Atomic Energy

International Nuclear Information System (INIS)

Marcus, F.

1990-01-01

Joint Nordic research programmes in nuclear safety have been conducted since 1977 under the direction of the Nordic Liaison Committee for Atomic Energy. Each of these four-year programmes is evaluated according to a procedure established by the Nordic Committee for Safety Research, NKS. The latest programme covered the period 1985-89 and included items that are of interest to countries that have nuclear power plants (Finland and Sweden) as well as to countries without (Denmark, Iceland and Norway). This last programme has been evaluated in 1990. The first area (AKT) deals with phenomena that might occur within the reactor containment during accidents. It also deals with potential pathways of radioactive material that could be released, as well as effects in the environment and possible counter-measures. The second area (KAV) investigates several topics related to waste management, such as waste arising in Scandinavia from power plant operation and decommissioning, and related transportation needs. It also deals with the methods used for modelling possible leaks from waste repositories and the uncertainty related to such calculations. The third area (RAS) deals with risk management - how decisions on safety issues are made, and what is the relative risk of nuclear activities. It also deals with methods for safety calculations that are based on a probabilistic approach. In the fourth area (MAT), the tendency of materials to develop cracks under tough external conditions is examined together with corrosion issues relevant to nuclear plants. Finally, the fifth area (INF) deals with the possibility of using modern information technology to support communication and decision making during emergency situations at compelx industrial plants. (author)

Nirex Safety Assessment Research Programme bibliography, 1987

International Nuclear Information System (INIS)

Cooper, M.J.; Hodgkinson, D.P.

1987-06-01

This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW). All work referred to has been funded, or partly funded, by UK Nirex Limited, previously known as the Nuclear Industry Radioactive Waste Executive (NIREX). The bibliography has been divided into two sections, a List of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the containers are emplaced, and the immediately adjacent geological formation disturbed by the construction of the repository. The far-field is the undisturbed geological formation between the near-field and the biosphere. (author)

Feasibility studies of safety assessment methods for programmable automation systems. Final report of the AVV project

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Pulkkinen, U.; Heikkinen, J.; Korhonen, J.; Tuulari, E.

1995-10-01

Feasibility studies of two different groups of methodologies for safety assessment of programmable automation systems has been executed at the Technical Research Centre of Finland (VTT). The studies concerned the dynamic testing methods and the fault tree (FT) and failure mode and effects analysis (FMEA) methods. In order to get real experience in the application of these methods, an experimental testing of two realistic pilot systems were executed and a FT/FMEA analysis of a programmable safety function accomplished. The purpose of the studies was not to assess the object systems, but to get experience in the application of methods and assess their potentials and development needs. (46 refs., 21 figs.)

Databases on safety issues for WWER and RBMK reactors. Users' manual. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-04-01

At the beginning of the IAEA Extrabudgetary Programme on the safety of WWER reactors a great number of findings and recommendations (safety items) were collected as a result of design review and safety review missions of the WWER-440/230 type reactors. On the basis of these findings a technical database containing more than 1300 records was established to support the consolidation of the information obtained and to help in identification of safety issues. After the scope of the WWER extrabudgetary programme was extended similar data sets were prepared for the WWER-440/213, WWER-1000 and RBMK nuclear power plants. This publication describes the structure of the databases on safety issues of WWER and RBMK NPPs, the information sources used in the databases and interrogation capabilities for users to obtain the necessary information. 14 refs, 9 figs, 5 tabs

Safety aspects of long term operation of water moderated reactors. Recommendations on the scope and content of programmes for safe long term operation. Final report of the extrabudgetary programme on safety aspects long term operation of water moderated reactors

International Nuclear Information System (INIS)

2007-07-01

During the last two decades, the number of IAEA Member States giving high priority to continuing the operation of nuclear power plants beyond the time frame originally anticipated is increasing. This is related to the age of nuclear power plants connected to the grid worldwide. The IAEA started to develop guidance on the safety aspects of ageing management in the 1990s. Recognizing the development in a number of its Member States, the IAEA initiated this Extrabudgetary Programme on Safety Aspects of Long Term Operation of Water Moderated Reactors in 2003. The objective of the Programme was to establish recommendations on the scope and content of activities to ensure safe long term operation of water moderated reactors. The term long term operation is used to accommodate various approaches in Member States and is defined as operation beyond an initial time frame set forth in design, standards, licence, and/or regulations, that is justified by safety assessment, considering life limiting processes and features for systems, structures and components. The scope of the Programme included general long term operation framework, mechanical components and materials, electrical components and instrumentation and control, and structural components and structures. The scope of the Programme was limited to physical structures of the NPPs. Four working groups addressed the above indicated technical areas. The Programme steering committee provided coordination and guidance and served as a forum for the exchange of information. The Programme implementation relied on voluntary in kind and financial contributions from the Czech Republic, Hungary, Slovakia, Sweden, the United Kingdom and the USA as well as in kind contributions from Bulgaria, Finland, the Netherlands, the Russian Federation, Spain, the Ukraine, and the European Commission. This report summarizes the main results, conclusions and recommendations of this Programme and provides in the Appendices I-IV detailed

Assessment by peer review of the effectiveness of a regulatory programme for radiation safety. Interim report for comment

International Nuclear Information System (INIS)

2002-06-01

This document covers assessment of those aspects of a radiation protection and safety infrastructure that are implemented by the Regulatory Authority for radiation sources and practices using such sources and necessarily includes those ancillary technical services, such as dosimetry services, which directly affect the ability of the Regulatory Authority to discharge its responsibilities. The focus of the guidance in this TECDOC is on assessment of a regulatory programme intended to implement the BSS. The BSS address transportation and waste safety mainly by reference to other IAEA documents. When conducting an assessment, the Review Team members should be aware of the latest IAEA documents (or similar national documents) concerning transportation and waste safety and, if appropriate, nuclear safety, and take them into account to the extent applicable when assessing the effectiveness of the regulatory programme governing radiation protection and safety of radiation source practices in a particular State

Assessment by peer review of the effectiveness of a regulatory programme for radiation safety. Interim report for comment

International Nuclear Information System (INIS)

2001-05-01

This document covers assessment of those aspects of a radiation protection and safety infrastructure that are implemented by the Regulatory Authority for radiation sources and practices using such sources and necessarily includes those ancillary technical services, such as dosimetry services, which directly affect the ability of the Regulatory Authority to discharge its responsibilities. The focus of the guidance in this TECDOC is on assessment of a regulatory programme intended to implement the BSS. The BSS address transportation and waste safety mainly by reference to other IAEA documents. When conducting an assessment, the Review Team members should be aware of the latest IAEA documents (or similar national documents) concerning transportation and waste safety and, if appropriate, nuclear safety, and take them into account to the extent applicable when assessing the effectiveness of the regulatory programme governing radiation protection and safety of radiation source practices in a particular State

Assuring safety without animal testing: Unilever's ongoing research programme to deliver novel ways to assure consumer safety.

Science.gov (United States)

Westmoreland, Carl; Carmichael, Paul; Dent, Matt; Fentem, Julia; MacKay, Cameron; Maxwell, Gavin; Pease, Camilla; Reynolds, Fiona

2010-01-01

Assuring consumer safety without the generation of new animal data is currently a considerable challenge. However, through the application of new technologies and the further development of risk-based approaches for safety assessment, we remain confident it is ultimately achievable. For many complex, multi-organ consumer safety endpoints, the development, evaluation and application of new, non-animal approaches is hampered by a lack of biological understanding of the underlying mechanistic processes involved. The enormity of this scientific challenge should not be underestimated. To tackle this challenge a substantial research programme was initiated by Unilever in 2004 to critically evaluate the feasibility of a new conceptual approach based upon the following key components: 1.Developing new, exposure-driven risk assessment approaches. 2.Developing new biological (in vitro) and computer-based (in silico) predictive models. 3.Evaluating the applicability of new technologies for generating data (e.g. "omics", informatics) and for integrating new types of data (e.g. systems approaches) for risk-based safety assessment. Our research efforts are focussed in the priority areas of skin allergy, cancer and general toxicity (including inhaled toxicity). In all of these areas, a long-term investment is essential to increase the scientific understanding of the underlying biology and molecular mechanisms that we believe will ultimately form a sound basis for novel risk assessment approaches. Our research programme in these priority areas consists of in-house research as well as Unilever-sponsored academic research, involvement in EU-funded projects (e.g. Sens-it-iv, Carcinogenomics), participation in cross-industry collaborative research (e.g. Colipa, EPAA) and ongoing involvement with other scientific initiatives on non-animal approaches to risk assessment (e.g. UK NC3Rs, US "Human Toxicology Project" consortium).

Nirex Safety Assessment Research Programme bibliography, 1988

International Nuclear Information System (INIS)

Cooper, M.J.

1988-05-01

This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. All work referred to has been funded, or partly funded, by UK Nirex Limited, previously known as the Nuclear Industry Radioactive Waste Executive (NIREX). The bibliography has been divided into two sections, a List of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the containers are emplaced, and the immediately adjacent geological formation disturbed by the construction of the repository. The far-field is the undisturbed geological formation between the near-field and the biosphere. (author)

Risk communication activities toward nuclear safety in Tokai: your safety is our safety

International Nuclear Information System (INIS)

Tsuchiya, T.

2007-01-01

As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C 3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C 3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

Applying the behaviour grid for improving safety in industrial environments

NARCIS (Netherlands)

Boer, de J. (Johannes); Heylen, D. (Dirk); Teeuw, W.B. (Wouter)

2013-01-01

The Saxion University of Applied Sciences recently started its “Safety at Work” project. Its objective is to increase safety in the workplace by combining and applying state-of-the-art factors from Ambient Intelligence, Industrial & Product Design and Smart Materials [1].The human

Emergency Diesel: Safety-related instrumentation and control with programmable logic controllers

International Nuclear Information System (INIS)

Breidenich, G.; Luedtke, M.

2004-01-01

This report presents a new concept for the design of emergency diesel equipment protection circuits as a part of the safety related instrumentation in the nuclear power plant Biblis, units A and B. The concept was implemented with state of the art SIMATIC S7/316 programmable logic controllers (PLCs) and can be adapted to any system with high availability requirements (e.g. power plant turbines, aircraft engines, mining pumps etc). (orig.)

Radiation protection training programmes Spanish approach

International Nuclear Information System (INIS)

Arboli, M. Marco; Suarez, M. Rodriguez; Cabrera, S. Falcon

2002-01-01

Radiation Protection Programmes are being considered the best way to promote safety culture and to spread and propagate European basic safety standards. It is widely accepted that training is an important tool to upgrade competence for radiation exposed workers. The Spanish Radiation Protection Education and Training Programmes provide a solid and integrated educational model, which takes into account the variety of applied fields, the different levels of responsibilities, the technological and methodological advances, as well as the international tendencies. The needs for a specialised training on Radiation Protection (RP) for exposed workers appears into the Spanish regulation in 1964. National initial training programmes are well established since 1972. Individual certifications, based on personal licences are required for exposed workers. The Spanish regulation also includes continuous and on the job RP training. The educational programmes are being continuously updating and improving. CIEMAT plays an important role in RP Spanish training, improving and modifying the previous RP courses and developing new programmes in order to complete the RP training levels. To achieve Radiation Protection objectives, new technological media for educational methods and material are taking into account. Nevertheless, Spanish RP education and training model has to be improved in some aspects. The purpose of this paper is to analyse the situation and the future needs to be considered in order to complete the RP training processes

Report of a consultants' meeting on insights from PSA results on the programmes for safety upgrading of WWER NPPs. Extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-11-01

The objective of the meeting was to compare the insight from plant specific PSA studies with the safety upgrading programme of WWER NPPs. The PSAs were reviewed considering the scope, level and detail of PSA models and results of IAEA peer reviews. Safety improvements which are not normally included in PSAs were also considered. The review specifically considers for each plant specific PSA: the dominant initiating events and accident sequences contributing to core damage; and, the importance of systems, components and human actions to be used for prioritizing actions. 4 refs, tabs

Fusion technology programme

International Nuclear Information System (INIS)

Finken, D.

1985-10-01

KfK is involved in the European Fusion Programme predominantly in the NET and Fusion Technology part. The following fields of activity are covered: Studies for NET, alternative confinement concepts, and needs and issues of integral testing. Research on structural materials. Development of superconducting magnets. Gyrotron development (part of the Physics Programme). Nuclear technology (breeding materials, blanket design, tritium technology, safety and environmental aspects of fusion, remote maintenance). Reported here are status and results of work under contracts with the CEC within the NET and Technology Programme. The aim of the major part of this R and D work is the support of NET, some areas (e.g. materials, safety and environmental impact, blanket design) have a wider scope and address problems of a demonstration reactor. In the current working period, several new proposals have been elaborated to be implemented into the 85/89 Euratom Fusion Programme. New KfK contributions relate to materials research (dual beam and fast reactor irradiations, ferritic steels), to blanket engineering (MHD-effects) and to safety studies (e.g. magnet safety). (orig./GG)

Principles underlying a guideline for applying HAZOP to programmable electronic systems

International Nuclear Information System (INIS)

Redmill, F.; Chudleigh, M.F.; Catmur, J.R.

1997-01-01

This paper reports on the experience of the authors, both in applying Hazard and Operability Studies (HAZOP) to programmable electronic systems (PES) and in researching the subject. A survey during the preparation of a guideline on the application of HAZOP to PES revealed common difficulties in this application. HAZOP is introduced, the difficulties are explained, and means of overcoming them are described

Evaluation of the fusion technology and safety programme of the Joint Research Centre (1980-85)

International Nuclear Information System (INIS)

Haines, M.; Cabibbo, N.; Crocker, J.G.; Lecomte, M.; Merz, E.

1986-01-01

The Joint Research Centre, Ispra, has been involved in fusion research since 1973. In July 1985 the Commission of European Communities - DG XII, following a policy of systematically evaluating its RandD activities, appointed a panel of external experts to evaluate the fusion technology and safety programme carried out at the Joint Research Centre. This report describes the work of the panel in evaluating the research performed by the JRC within the framework of its 1984-87 programme. The achievements of the previous programme, 1980-83, were also taken into consideration. The different research areas covered in the programme, i.e.: reactor studies, breeding blanket technology, structural materials studies, risk assessment and tritium laboratory studies, are described and a draft proposal for the period 1987-90 presented. The evaluation panel has been asked to assess the following aspects: the scientific and technical achievements of the programme, the contribution of the programme to the development of other Community policies, the role played by the JRC in the European fusion research (including NET) and in international collaborations such as INTOR. From its assessment the evaluation panel has made a series of recommendations for the current programme and for future work

ISAM news. International programme on implementation of safety assessment methodologies for near surface disposal facilities for radioactive waste (ISAM 1997-1999)

International Nuclear Information System (INIS)

Torres, Carlos

1996-01-01

The scope of the programme will be the scientific and technical aspects related to the long term safety assessment of near disposal facilities. The primary focus of ISAM will be on the methodological aspects of safety assessment with emphasis on the practical application of these methodologies. Furthermore, practical application is necessary for for a thorough understanding of safety assessment methodologies. The programme will address important methodological issues associated with long term safety assessment of near surface disposal systems. At least three important areas will be covered: (1) scenario generation and justification; (2) modelling, data and tools; and (3) analysis of results and confidence building

Applied Health Physics and Safety annual report for 1975

International Nuclear Information System (INIS)

1976-08-01

This report describes and summarizes the activities of the applied sections and/or groups of the Health Physics Division. Projects and activities covered include personnel monitoring, environmental monitoring, radiation and safety surveys, and industrial safety

Nuclear safety. Seguranca nuclear

Energy Technology Data Exchange (ETDEWEB)

Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

1981-01-01

What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

Center for Food Safety and Applied Nutrition

Data.gov (United States)

Federal Laboratory Consortium — The Center for Food Safety and Applied Nutrition, known as CFSAN, is one of six product-oriented centers, in addition to a nationwide field force, that carry out the...

Estimating dependability of programmable systems using bayesian belief nets

International Nuclear Information System (INIS)

Gran, Bjoern Axel; Dahll, Gustav

2000-05-01

The research programme at the Halden Project on software safety assessment is augmented through a joint project with Kongsberg Defence and Aerospace AS and Det Norske Veritas. The objective of this project is to investigate the possibility to combine the Bayesian Belief Net (BBN) methodology with a software safety standard. The report discusses software safety standards in general, with respect to how they can be used to measure software safety. The possibility to transfer the requirements of a software safety standard into a BBN is also investigated. The aim is to utilise the BBN methodology and associated tools, by transferring the software safety measurement into a probabilistic quantity. In this way software can be included in a total probabilistic safety analysis. This project was performed by applying the method for an evaluation of a real, safety related programmable system which was developed according to the avionic standard DO-178B. The test case, the standard, and the BBN methodology are shortly described. This is followed by a description of the construction of the BBN used in this project. This includes the topology of the BBN, the elicitation of probabilities and the making of observations. Based on this a variety of computations are made using the SERENE methodology and the HUGIN tool. Observations and conclusions are made on the basis of the findings from this process. This report should be considered as a progress report in a more long-term activity on the use of BBNs as support for safety assessment of programmable systems. (Author). 23 refs., 9 figs., tabs

Validation of programmable industrial automation systems for safety critical applications in NPP's; dynamic testing

International Nuclear Information System (INIS)

Haapanen, P.; Korhonen, J.

1995-01-01

The safety assessment of programmable automation systems cannot be totally be based on conventional probabilistic methods because of the difficulties in quantification of the reliability of the software as well as the hardware. Additional means shall therefore be used to gain more confidence on the system dependability. One central confidence building measure is the independent dynamic testing of the completed system. An automated test harness is needed to run the required large amount of test cases in a restricted time span. This paper describes a prototype dynamic testing harness for programmable digital systems developed at VTT. (author). 12 refs, 2 figs, 2 tabs

The role of intermediaries in delivering an occupational health and safety programme designed for small business - a case study of an insurance incentive programme in the agriculture sector

DEFF Research Database (Denmark)

Olsen, Kirsten Bendix; Hasle, Peter

2015-01-01

to the transformation and dissemination of a national OHS programme for small business that built on an Insurance incentive scheme – the New Zealand Workplace Safety Discount scheme. It is a case study of this scheme implementation in the agriculture sector. Data was collected from scheme documentation and semi......-structured interviews with the scheme owner, representatives from intermediary groups and the targeted small businesses. The interviews were tape recorded, transcribed and thematically analysed in relation to the scheme’s programme theory. The intermediaries introduced new programme mechanisms and recruitment...

Status of the safety certification process of the TRANSRAPID system

Energy Technology Data Exchange (ETDEWEB)

Blomerius, J [TUEV Rheinland, Koeln (Germany). Inst. fuer Software, Elektronik, Bahntechnik

1996-12-31

Since 20 years TUeV Rheinland is involved in safety certification of maglev technology of the TRANSRAPID type. The process applied is called PASC (Programm Accompanying Safety Certification). The paper reports on safety assessment of relevant subsystems and components (TR07, OCS, guideway components) as well as safety certification in the final program. (HW)

FBR's safety: main results, problems to solve and corresponding programmes in France

International Nuclear Information System (INIS)

Justin, F.; Meyer-Heine, A.; Natta, M.; Penet, F.

1979-08-01

The safety demonstration of the first large fast breeder reactor in France was based on existing tests and on a programme of studies. The condition to license was the regular providing of some intermediate results to authorities. This continuous procedure is developed and examples are given of complementary measures when results are not in compliance with previsions. The start-up of the plant and its operating conditions will depend on the availability of necessary information

An overview of review guidelines for HDL programmable devices in nuclear safety systems

International Nuclear Information System (INIS)

Komanduri, Raghavan; Srivani, L.; Thirugnana Murthy, D.

2013-01-01

HDL programmable devices viz. CPLDs and FPGAs are increasingly being used to implement digital designs in the I and C systems performing safety functions of nuclear power plants. Synthesizable RTL descriptions manually written in HDLs are the first step in developing industry standard large scale digital designs. The reliability of the implementation is determined by the methodologies followed by the designer during development. Very few guidelines on HPD design practices, specific to nuclear industry are available. This paper presents an overview of the existing guidelines such as IEC 62566 and U.S. NRC's 'Review guidelines for FPGAs in nuclear power plant safety systems'. (author)

A Development of the Calibration Tool Applied on Analog I/O Modules for Safety-related Controller

International Nuclear Information System (INIS)

Kim, Jong-Kyun; Yun, Dong-Hwa; Lee, Myeong-Kyun; Yoo, Kwan-Woo

2016-01-01

The purpose of this paper is to develop the calibration tool for analog input/output(I/O) modules. Those modules are components in POSAFE-Q which is a programmable logic controller(PLC) that has been developed for the evaluation of safety-related. In this paper, performance improvement of analog I/O modules is presented by developing and applying the calibration tool for each channel in analog I/O modules. With this tool, the input signal to an analog input module and the output signal from an analog output module are able to be satisfied with a reference value of sensor type and an accuracy of all modules. With RS-232 communication, the manual calibration tool is developed for analog I/O modules of an existing and up-to-date version in POSAFE-Q PLC. As a result of applying this tool, the converted value is performant for a type of input sensor and an accuracy of analog I/O modules

Validation of programmable industrial automation systems for safety critical applications in NPP's dynamic testing

International Nuclear Information System (INIS)

Haapanen, P.; Korhonen, J.

1995-01-01

The safety assessment of programmable automation systems can not totally be based on conventional probabilistic methods because of the difficulties in quantification of the reliability of the software as well as the hardware. Additional means shall therefore be used to gain more confidence on the system dependability. One central confidence building measure is the independent dynamic testing of the completed system. An automated test harness is needed to run the required large amount of test cases in a restricted time span. The prototype dynamic testing harness for programmable digital systems developed at the Technical Research Centre of Finland (VTT) is described in the presentation. (12 refs., 2 figs., 2 tabs.)

Developing international alumni activities in Mikkeli University of Applied Sciences : Case Business Management degree programme

OpenAIRE

Honkaniemi, Meri

2014-01-01

My thesis focuses on international alumni activities in Mikkeli University of Applied Sciences. My aim was to find development ideas and recommendations for the international side of the alumni activities. I intended to offer realistic suggestions enough in order to make them work in practice too. I put also my effort on finding recommendations for Business Management programme, because I wanted to make sure that international alumni activities get attention in degree programme level too. ...

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2006-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

A 'Communication and Patient Safety' training programme for all healthcare staff: can it make a difference?

Science.gov (United States)

Lee, Peter; Allen, Kellie; Daly, Michael

2012-01-01

Communication breakdown is a factor contributing to most cases of patient harm, and this harm continues to occur at unacceptable levels. Responding to this evidence, the Metro South District of Queensland Health (Australia) has developed a communication skills training programme titled 'Communication and Patient Safety'. The three modules, each lasting 3½ h, cover both staff-to-patient and staff-to-staff communication issues, and an unusual feature is that clinical and non-clinical staff attend together. Following positive evaluation data from our initial pilot programme (involving 350 staff in a single hospital), the programme was expanded to all five hospitals in the district, and has now been completed by over 3000 staff. The results show that despite the significant time commitment, participants find the courses useful and relevant (Kirkpatrick level 1), they learn and retain new material (level 2), and they report changes in behaviour at individual, team and facility levels (level 3). Although it remains a challenge to obtain quantitative data showing that training such as this directly improves patient safety (level 4), our qualitative and informal feedback indicates that participants and their managers perceive clear improvements in the 'communication culture' after a workplace team has attended the courses. Improving 'communication for safety' in healthcare is a worldwide imperative, and other healthcare jurisdictions should be able to obtain similar results to ours if they develop and support interactive, non-didactic training in communication skills.

Verification of FPGA-Signal using the test board which is applied to Safety-related controller

Energy Technology Data Exchange (ETDEWEB)

Chung, Youn-Hu; Yoo, Kwanwoo; Lee, Myeongkyun; Yun, Donghwa [SOOSAN ENS, Seoul (Korea, Republic of)

2016-10-15

This article aims to provide the verification method for BGA-type FPGA of Programmable Logic Controller (PLC) developed as Safety Class. The logic of FPGA in the control device with Safety Class is the circuit to control overall logic of PLC. Saftety-related PLC must meet the international standard specifications. With this reason, we use V and V according to an international standard in order to secure high reliability and safety. By using this, we are supposed to proceed to a variety of verification courses for extra reliability and safety analysis. In order to have efficient verification of test results, we propose the test using the newly changed BGA socket which can resolve the problems of the conventional socket on this paper. The Verification of processes is divided into verification of Hardware and firmware. That processes are carried out in the unit testing and integration testing. The proposed test method is simple, the effect of cost reductions by batch process. In addition, it is advantageous to measure the signal from the Hi-speed-IC due to its short length of the pins and it was plated with the copper around it. Further, it also to prevent abrasion on the IC ball because it has no direct contact with the PCB. Therefore, it can be actually applied is to the BGA package test and we can easily verify logic as well as easily checking the operation of the designed data.

RATU Nuclear power plant structural safety research programme 1990-1994. Final report

International Nuclear Information System (INIS)

Rintamaa, R.; Sarkimo, M.

1995-12-01

The major part of nuclear energy research in Finland has been organized as five-year nationally coordinated research programmes. The research programme on the Nuclear Power Plant Structural Safety was carried out during the period from 1990 to 1994. The total volume was about 76 person-years and the expenditure about 49 million FIM. Studies on the structural materials in nuclear power plants created the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research was carried out by developing experimental fracture mechanics methods including statistical analysis methods of material property data, and by studying material ageing and, in particular, mechanisms of material deterioration due to neutron irradiation, corrosion and water chemistry. Besides material studies, new testing methods and sensors for the measurement of loading and water chemistry parameters have been developed

[Learning from errors: applying aviation safety concepts to medicine].

Science.gov (United States)

Sommer, K-J

2012-11-01

Health care safety levels range below other complex industries. Civil aviation has throughout its history developed methods and concepts that have made the airplane into one of the safest means of mass transport. Key elements are accident investigations that focus on cause instead of blame, human-centered design of machinery and processes, continuous training of all personnel and a shared safety culture. These methods and concepts can basically be applied to medicine which has successfully been achieved in certain areas, however, a comprehensive implementation remains to be completed. This applies particularly to including the topic of safety into relevant curricula. Physicians are obliged by the oath"primum nil nocere" to act, but economic as well as political pressure will eventually confine professional freedom if initiative is not taken soon.

Safety Priorities and Underestimations in Recreational Scuba Diving Operations: A European Study Supporting the Implementation of New Risk Management Programmes

Directory of Open Access Journals (Sweden)

Serena Lucrezi

2018-03-01

Full Text Available Introduction: Scuba diving is an important marine tourism sector, but requires proper safety standards to reduce the risks and increase accessibility to its market. To achieve safety goals, safety awareness and positive safety attitudes in recreational scuba diving operations are essential. However, there is no published research exclusively focusing on scuba divers’ and dive centres’ perceptions toward safety. This study assessed safety perceptions in recreational scuba diving operations, with the aim to inform and enhance safety and risk management programmes within the scuba diving tourism industry.Materials and Methods: Two structured questionnaire surveys were prepared by the organisation Divers Alert Network and administered online to scuba diving operators in Italy and scuba divers in Europe, using a mixture of convenience and snowball sampling. Questions in the survey included experience and safety offered at the dive centre; the buddy system; equipment and accessories for safe diving activities; safety issues in the certification of new scuba divers; incidents/accidents; and attitudes toward safety.Results: 91 scuba diving centres and 3,766 scuba divers participated in the study. Scuba divers gave importance to safety and the responsiveness of service providers, here represented by the dive centres. However, they underestimated the importance of a personal emergency action/assistance plan and, partly, of the buddy system alongside other safety procedures. Scuba divers agreed that some risks, such as those associated with running out of gas, deserve attention. Dive centres gave importance to aspects such as training and emergency action/assistance plans. However, they were limitedly involved in safety campaigning. Dive centres’ perceptions of safety in part aligned with those of scuba divers, with some exceptions.Conclusion: Greater responsibility is required in raising awareness and educating scuba divers, through participation in

Safety Priorities and Underestimations in Recreational Scuba Diving Operations: A European Study Supporting the Implementation of New Risk Management Programmes

Science.gov (United States)

Lucrezi, Serena; Egi, Salih Murat; Pieri, Massimo; Burman, Francois; Ozyigit, Tamer; Cialoni, Danilo; Thomas, Guy; Marroni, Alessandro; Saayman, Melville

2018-01-01

Introduction: Scuba diving is an important marine tourism sector, but requires proper safety standards to reduce the risks and increase accessibility to its market. To achieve safety goals, safety awareness and positive safety attitudes in recreational scuba diving operations are essential. However, there is no published research exclusively focusing on scuba divers’ and dive centres’ perceptions toward safety. This study assessed safety perceptions in recreational scuba diving operations, with the aim to inform and enhance safety and risk management programmes within the scuba diving tourism industry. Materials and Methods: Two structured questionnaire surveys were prepared by the organisation Divers Alert Network and administered online to scuba diving operators in Italy and scuba divers in Europe, using a mixture of convenience and snowball sampling. Questions in the survey included experience and safety offered at the dive centre; the buddy system; equipment and accessories for safe diving activities; safety issues in the certification of new scuba divers; incidents/accidents; and attitudes toward safety. Results: 91 scuba diving centres and 3,766 scuba divers participated in the study. Scuba divers gave importance to safety and the responsiveness of service providers, here represented by the dive centres. However, they underestimated the importance of a personal emergency action/assistance plan and, partly, of the buddy system alongside other safety procedures. Scuba divers agreed that some risks, such as those associated with running out of gas, deserve attention. Dive centres gave importance to aspects such as training and emergency action/assistance plans. However, they were limitedly involved in safety campaigning. Dive centres’ perceptions of safety in part aligned with those of scuba divers, with some exceptions. Conclusion: Greater responsibility is required in raising awareness and educating scuba divers, through participation in prevention

Safety Priorities and Underestimations in Recreational Scuba Diving Operations: A European Study Supporting the Implementation of New Risk Management Programmes.

Science.gov (United States)

Lucrezi, Serena; Egi, Salih Murat; Pieri, Massimo; Burman, Francois; Ozyigit, Tamer; Cialoni, Danilo; Thomas, Guy; Marroni, Alessandro; Saayman, Melville

2018-01-01

Introduction: Scuba diving is an important marine tourism sector, but requires proper safety standards to reduce the risks and increase accessibility to its market. To achieve safety goals, safety awareness and positive safety attitudes in recreational scuba diving operations are essential. However, there is no published research exclusively focusing on scuba divers' and dive centres' perceptions toward safety. This study assessed safety perceptions in recreational scuba diving operations, with the aim to inform and enhance safety and risk management programmes within the scuba diving tourism industry. Materials and Methods: Two structured questionnaire surveys were prepared by the organisation Divers Alert Network and administered online to scuba diving operators in Italy and scuba divers in Europe, using a mixture of convenience and snowball sampling. Questions in the survey included experience and safety offered at the dive centre; the buddy system; equipment and accessories for safe diving activities; safety issues in the certification of new scuba divers; incidents/accidents; and attitudes toward safety. Results: 91 scuba diving centres and 3,766 scuba divers participated in the study. Scuba divers gave importance to safety and the responsiveness of service providers, here represented by the dive centres. However, they underestimated the importance of a personal emergency action/assistance plan and, partly, of the buddy system alongside other safety procedures. Scuba divers agreed that some risks, such as those associated with running out of gas, deserve attention. Dive centres gave importance to aspects such as training and emergency action/assistance plans. However, they were limitedly involved in safety campaigning. Dive centres' perceptions of safety in part aligned with those of scuba divers, with some exceptions. Conclusion: Greater responsibility is required in raising awareness and educating scuba divers, through participation in prevention campaigns

Ward based community road safety performance benchmarking, monitoring and intervention programmes in the City of Johannesburg

CSIR Research Space (South Africa)

Ribbens, H

2008-07-01

Full Text Available benchmarking, monitoring and intervention programme. Community road safety needs in the respective wards are articulated through the ward councillor. The rationale is that the community exactly knows where these problem areas are, because they suffer as a...

Emerging standards with application to accelerator safety systems

International Nuclear Information System (INIS)

Mahoney, K.L.; Robertson, H.P.

1997-01-01

This paper addresses international standards which can be applied to the requirements for accelerator personnel safety systems. Particular emphasis is given to standards which specify requirements for safety interlock systems which employ programmable electronic subsystems. The work draws on methodologies currently under development for the medical, process control, and nuclear industries

Finnish Research Programme on Nuclear Waste Management (KYT). Framework Programme for 2002-2005

International Nuclear Information System (INIS)

Rasilainen, K.

2002-12-01

The new Finnish research programme on nuclear waste management (KYT) will be conducted in 2002 - 2005. This framework programme describes the starting point, the basic aims and the organisation of the research programme. The starting point of the KYT programme is derived from the present state and future challenges of Finnish nuclear waste management. The research programme is funded mainly by the Ministry of Trade and Industry (KTM), the Radiation and Nuclear Safety Authority (STUK), Posiva Oy, Fortum Oyj, Teollisuuden Voima Oy (TVO), and the National Technology Agency (Tekes). As both regulators and implementors are involved, the research programme concentrates on neutral research topics that must be studied in any case. Methods and tools for experimental and theoretical studies fall in this category. State of the art -reviews on relevant topics also create national know-how. Topics that directly belong to licensing activities of nuclear waste management are excluded from the research programme. KYT carries out technical studies that increase national know-how in the area of nuclear waste management. The aim is to maintain and develop basic expertise needed in the operations derived from the national nuclear waste management plan. The studies have been divided into strategic studies and studies enhancing the long-term safety of spent nuclear fuel disposal. Strategic studies support the overall feasibility of Finnish nuclear waste management. These studies include basic options and overall safety principles related to nuclear fuel cycle and nuclear waste management. In addition, general cost estimates as well as general safety considerations related to transportations, low- and medium level wastes, and decommissioning are included in strategic studies. Studies supporting the long-term safety of spent fuel disposal include issues related to performance assessment methodology, release of radionuclides from the repository, behaviour of bedrock and groundwater

Software V and V methods for a safety - grade programmable logic controller

International Nuclear Information System (INIS)

Jang Yeol Kim; Young Jun Lee; Kyung Ho Cha; Se Woo Cheon; Jang Soo Lee; Kee Choon Kwon

2006-01-01

This paper addresses the Verification and Validation(V and V) process and the methodology for an embedded real time software of a safety-grade Programmable Logic Controller(PLC). This safety- grade PLC is being developed as one of the Korean Nuclear Instrumentation and Control System (KNICS) projects. KNICS projects are developing a Reactor Protection System(RPS) and an Engineered Safety Feature-Component Control System(ESF-CCS) as well as a safety-grade PLC. The safety-grade PLC will be a major component that encomposes the RPS systems and the ESF-CCS systems as nuclear instruments and control equipment. This paper describes the V and V guidelines and procedures, V and V environment, V and V process and methodology, and the V and V tools in the KNICS projects. Specifically, it describes the real-time operating system V and V experience which corresponds to the requirement analysis phase, design phase and the implementation and testing phase of the software development life cycle. Main activities of the V and V for the PLC system software are a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and a software configuration management. The proposed V and V methodology satisfies the Standard Review Plan(SRP)/Branch Technical Position(BTP)-14 criteria for the safety software in nuclear power plants. The proposed V and V methodology is going to be used to verify the upcoming software life cycle in the KNICS projects. (author)

RBMK nuclear power plants: Generic safety issues. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-05-01

This report has been prepared on the basis of above mentioned report and it is intended to provide information on RBMK NPPs generic safety issues. As all other insights, recommendations and conclusions resulting from the IAEA Programme, this report is intended to assist national decision makers, who have sole responsibility for the regulation and safe operation of their nuclear power plants. It also serves to focus national and international projects on priority of the RBMK safety improvements. 23 refs, 10 figs, 3 tabs

The Nordic programme for nuclear safety 1990-1993. Report for 1992

International Nuclear Information System (INIS)

1993-04-01

The annual report contains the coordinators' summary of the results so far achieved by the in all 18 current projects in which 200 persons are taking part. In some cases the project leader's account is included. An overview is given of the programme's costs and orders during 1992 in relation to the subsidies given to the individual projects. The fields covered by these projects are emergency readiness in radiation situations which are not normal, nuclear wastes and their disposal, radioecology, reactor safety - knowledge readiness, and coordination efforts. An economical overview is given and English summaries of the projects presented at the summer meeting in 1992 are presented. A list of the names of the members of the Nordic Nuclear Safety Research members in the syndicate and reference groups is included in the publication, and a brief description is to be found of the institution's activities. (AB) (78 refs.)

Nirex safety assessment research programme bibliography, 1991

International Nuclear Information System (INIS)

Cooper, M.J.

1991-09-01

This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. The bibliography has been divided into two sections, a list of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste package, filling or sealing materials, and those parts of the host medium whose characteristics have been or could be altered by the repository or its content. The far-field is the rock formation outside the repository, including the surrounding strata, at a distance from the waste disposal site such that, for modelling purposes, the site may be considered as a single entity, and the effects of individual waste packages are indistinguishable in the effects of the whole. The far-field includes also the biosphere, into which radionuclides from the waste could conceivably migrate in the future. (author)

Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

International Nuclear Information System (INIS)

1994-01-01

The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Evaluation of the patient safety Leadership Walkabout programme of a hospital in Singapore.

Science.gov (United States)

Lim, Raymond Boon Tar; Ng, Benjamin Boon Lui; Ng, Kok Mun

2014-02-01

The Patient Safety Leadership Walkabout (PSLWA) programme is a commonly employed tool in the West, in which senior leaders visit sites within the hospital that are involved in patient care to talk to healthcare staff about patient safety issues. As there is a lack of perspective regarding PSLWA in Asia, we carried out an evaluation of its effectiveness in improving the patient safety culture in Tan Tock Seng Hospital, Singapore. A mixed methods analysis approach was used to review and evaluate all documents, protocols, meeting minutes, post-walkabout surveys, action plans and verbal feedback pertaining to the walkabouts conducted from January 2005 to October 2012. A total of 321 patient safety issues were identified during the study period. Of these, 308 (96.0%) issues were resolved as of November 2012. Among the various categories of issues raised, issues related to work environment were the most common (45.2%). Of all the issues raised during the walkabouts, 72.9% were not identified through other conventional methods of error detection. With respect to the hospital's patient safety culture, 94.8% of the participants reported an increased awareness in patient safety and 90.2% expressed comfort in openly and honestly discussing patient safety issues. PSLWA serves as a good tool to uncover latent errors before actual harm reaches the patient. If properly implemented, it is an effective method for engaging leadership, identifying patient safety issues, and supporting a culture of patient safety in the hospital setting.

The safety of WWER and RBMK nuclear power plants. Progress report on the IAEA extrabudgetary programme on the safety of WWER and RBMK nuclear power plants, 1992-1994

International Nuclear Information System (INIS)

1994-11-01

This report, prepared by the IAEA secretariat, provides an overview of the IAEA Extrabudgetary Programme activities and results from 1992 until June 1994. The report describes the scope, the current status of the implementation and major findings and recommendations of the Programme. Though this report concentrates on the results of the Extrabudgetary Programme, it also refers to the significant related activities carried out under IAEA Technical Co-operation projects, as well as other international activities relevant to the safety of WWER and RBMK reactors. 13 figs, 9 tabs

THAI experimental programme for containment safety assessment under severe accident conditions

Energy Technology Data Exchange (ETDEWEB)

Gupta, S.; Freitag, M. [Becker Technologies GmbH, Eschborn (Germany); Poss, G.

2016-05-15

The THAI (THAI = Thermal hydraulics, Hydrogen, Aerosols, Iodine) experimental programme aims to address open questions concerning the behavior of hydrogen, iodine and aerosols in the containment of water cooled reactors. Since its construction in 2000, THAI programme is being performed in the frame of various national projects (sponsored by German Federal Ministry for Economic Affairs and Energy, BMWi) and two international joint projects (under auspices of OECD/NEA). THAI experimental data have been widely used for the validation and further development of Lumped Parameter (LP) and Computational Fluid Dynamics (CFD) codes with 3D capabilities. Selected examples of code benchmark exercises performed based on the THAI data include; hydrogen distribution experiment (ISP-47 and OECD/NEA THAI code benchmark), hydrogen combustion behaviour (ISP-49), hydrogen mitigation by PARs (OECD/NEA THAI-2 code benchmark), iodine/surface interactions, iodine mass transfer, and iodine transport and multi-compartment behaviour (EU-SARNET and EU-SARNET2), thermal-hydraulic tests (German CFD-network). In the present paper, a brief overview on the THAI experiments and their role in the containment safety assessment is discussed.

Strengths, weaknesses, opportunities and threats – swot analysis regarding the romanian participation in euratom programmes on nuclear safety topic

International Nuclear Information System (INIS)

Apostol, M.; Constantin, M.; Diaconu, D.

2013-01-01

In the frame of FP7 - NEWLANCER project, SWOT analysis (Strengths, Weaknesses, Opportunities and Threats) was performed by each partner from New Member States (NMS) in order to provide valuable input for the development of policies aimed to increase the participation of the NMS in Euratom programmes on the following topics: Generation III and IV systems and materials, Nuclear safety, Radioprotection, Radioactive waste management, and Education and training. The final objective of SWOT analysis performed by National Expert Groups on Nuclear Safety (NS) topic was to propose strategies, in order to reduce the influence of identified negative factors and to enhance influence of identified positive factors, regarding Romanian participation in Euratom programmes. (authors)

Radiation and waste safety

International Nuclear Information System (INIS)

1997-01-01

Most of the ionizing radiation that people are exposed to in day-to-day activities comes from natural, rather than manmade, sources. Nuclear radiation is a powerful source of benefit to mankind, whether applied in the field of medicine, agriculture, environmental management or elsewhere. The health effects of radiation - both natural and artificial - are relatively well understood and can be minimized through careful safety measures and practices. The Department of Technical Co-operation is sponsoring a programme with the support of the Nuclear Safety Department aiming at establishing Basic Safety Standard requirements in all Member States. (IAEA)

Seminar on the use of research reactors in fundamental and applied sciences. Programme and abstracts

International Nuclear Information System (INIS)

1984-01-01

The document includes the programme and the abstracts of papers presented at the ''Seminar on the use of research reactors in fundamental and applied sciences'' organized by the Tajoura Nuclear Research Centre in cooperation with the IAEA at Tajoura, Tripoli (Libya) between 16-20 September 1984. The abstracts are grouped in seven sessions: reactor physics (five abstracts), research reactor programmes (three abstracts), solid state physics (two abstracts), nuclear physics (two abstracts), radiochemistry (eleven abstracts), activation analysis (five abstracts), diverse topics (six abstracts). Separate indexing was provided for each abstract

Applying importance-performance analysis to patient safety culture.

Science.gov (United States)

Lee, Yii-Ching; Wu, Hsin-Hung; Hsieh, Wan-Lin; Weng, Shao-Jen; Hsieh, Liang-Po; Huang, Chih-Hsuan

2015-01-01

The Sexton et al.'s (2006) safety attitudes questionnaire (SAQ) has been widely used to assess staff's attitudes towards patient safety in healthcare organizations. However, to date there have been few studies that discuss the perceptions of patient safety both from hospital staff and upper management. The purpose of this paper is to improve and to develop better strategies regarding patient safety in healthcare organizations. The Chinese version of SAQ based on the Taiwan Joint Commission on Hospital Accreditation is used to evaluate the perceptions of hospital staff. The current study then lies in applying importance-performance analysis technique to identify the major strengths and weaknesses of the safety culture. The results show that teamwork climate, safety climate, job satisfaction, stress recognition and working conditions are major strengths and should be maintained in order to provide a better patient safety culture. On the contrary, perceptions of management and hospital handoffs and transitions are important weaknesses and should be improved immediately. Research limitations/implications - The research is restricted in generalizability. The assessment of hospital staff in patient safety culture is physicians and registered nurses. It would be interesting to further evaluate other staff's (e.g. technicians, pharmacists and others) opinions regarding patient safety culture in the hospital. Few studies have clearly evaluated the perceptions of healthcare organization management regarding patient safety culture. Healthcare managers enable to take more effective actions to improve the level of patient safety by investigating key characteristics (either strengths or weaknesses) that healthcare organizations should focus on.

A novel safety assessment strategy applied to non-selective extracts.

Science.gov (United States)

Koster, Sander; Leeman, Winfried; Verheij, Elwin; Dutman, Ellen; van Stee, Leo; Nielsen, Lene Munch; Ronsmans, Stefan; Noteborn, Hub; Krul, Lisette

2015-06-01

A main challenge in food safety research is to demonstrate that processing of foodstuffs does not lead to the formation of substances for which the safety upon consumption might be questioned. This is especially so since food is a complex matrix in which the analytical detection of substances, and consequent risk assessment thereof, is difficult to determine. Here, a pragmatic novel safety assessment strategy is applied to the production of non-selective extracts (NSEs), used for different purposes in food such as for colouring purposes, which are complex food mixtures prepared from reference juices. The Complex Mixture Safety Assessment Strategy (CoMSAS) is an exposure driven approach enabling to efficiently assess the safety of the NSE by focussing on newly formed substances or substances that may increase in exposure during the processing of the NSE. CoMSAS enables to distinguish toxicologically relevant from toxicologically less relevant substances, when related to their respective levels of exposure. This will reduce the amount of work needed for identification, characterisation and safety assessment of unknown substances detected at low concentration, without the need for toxicity testing using animal studies. In this paper, the CoMSAS approach has been applied for elderberry and pumpkin NSEs used for food colouring purposes. Copyright © 2015 Elsevier Ltd. All rights reserved.

Evaluation of safety practices and performance in a brewery industry ...

African Journals Online (AJOL)

Evaluation of safety practices and performance in a brewery industry in Nigeria between 2000 – 2007. ... Journal of Applied Sciences and Environmental Management ... The study revealed that a total of 156 accidents were prevented in the period of the safety programme which translates to an average of 19.45 per year.

Seismic safety of nuclear power plants

International Nuclear Information System (INIS)

Guerpinar, A.; Godoy, A.

2001-01-01

This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on 'Benchmark study for the seismic analysis and testing of WWER type nuclear power plants'. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

The role of the regulator in promoting and evaluating safety culture. Operating experience feedback programme approach

International Nuclear Information System (INIS)

Perez, S.

2002-01-01

Promoting and Evaluating Safety Culture (S.C.) in Operating Organizations must be one of the main Nuclear Regulator goals to achieve. This can be possible only if each and every one of the regulatory activities inherently involves S.C. It can be seen throughout attitudes, values, uses and practices in both individuals and the whole regulatory organization. One among all the regulatory tools commonly used by regulators to promote and evaluate the commitment of the licensees with safety culture as a whole involves organizational factors and particular attention is directed to the operating organization. This entailed a wide range of activities, including all those related with management of safety performance. Operating Experience Feedback Programme as a tool to enhance safety operation is particularly useful for regulators in the evaluation of the role of S.C. in operating organization. Safety Culture is recognized as a subset of the wider Organizational Culture. Practices that improve organizational effectiveness can also contribute to enhance safety. An effective event investigation methodology is a specific practice, which contributes to a healthy Safety Culture. (author)

Radiological safety programme for the health departments in Parana, Brazil

International Nuclear Information System (INIS)

Schmidt, M.F.S.; Tilly, J.G. Jr.

1998-01-01

As a result of Brazil's centralized administration in the past, various parts of the public service were somewhat inefficient. Another reason was the size of the country. To improve the situation in the health sector, it was decided to transfer administrative responsibility to the municipal authorities. Accordingly, the public health system is now defined under the appropriate legislation as the 'Unified Health System' (SUS), comprising federal, state and municipal levels. This system promotes decentralization of therapeutic or preventive services (including the Radiation Facility Health Inspectorate) and proposes any additional legislation required. In Parana the Radiation Facility Health Inspectorate has 3600 organizations listed, employing ionizing radiation in medicine, industry and research, which need to be regularly inspected for licensing and control. In 1994, 50% of the annual inspection target in the state was attained. The Radiation Safety Programme for the Health Departments in Parana directs these activities in this State. Its strategies are: (1) to establish implementation phases for activities planned for each area; (2) to take advantage of the SUS structure to introduce or expand operational services at the primary, secondary and tertiary levels with appropriate equipment. The tertiary level involves co-ordination of the Programme and complementary executive functions, as well as maintaining an information system with other related organizations. The other levels include licensing, control and emergency response. As the Programme develops, indicators will be established to help identify progress achieved and correct operating strategy where necessary. Thus, the services provided to the public will be enhanced in quality and the radiation doses reduced. In addition, in emergency situations, the time elapsing between the event and its notification to the authorities will be reduced, minimizing the consequences of any accidents. (author)

HSE Nuclear Safety Research Program

Energy Technology Data Exchange (ETDEWEB)

Bagley, M.J. [Health and Safety Executive, Sheffield (United Kingdom)

1995-12-31

HSE funds two programmes of nuclear safety research: a programme of {approx} 2.2M of extramural research to support the Nuclear Safety Division`s regulatory activities and a programme of {approx} 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author).

HSE Nuclear Safety Research Program

International Nuclear Information System (INIS)

Bagley, M.J.

1995-01-01

HSE funds two programmes of nuclear safety research: a programme of ∼ 2.2M of extramural research to support the Nuclear Safety Division's regulatory activities and a programme of ∼ 11M of generic safety research managed by the Nuclear Safety Research Management Unit (NSRMU) in Sheffield, UK. This paper is concerned only with the latter programme; it describes how it is planned and procured and outlines some of the work on structural integrity problems. It also describes the changes that are taking place in the way nuclear safety research is procured in the UK. (author)

The Qualification Experiences for Safety-critical Software of POSAFE-Q

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Yeol; Son, Kwang Seop; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-05-15

Programmable Logic Controllers (PLC) have been applied to the Reactor Protection System (RPS) and the Engineered Safety Feature (ESF)-Component Control System (CCS) as the major safety system components of nuclear power plants. This paper describes experiences on the qualification of the safety-critical software including the pCOS kernel and system tasks related to a safety-grade PLC, i.e. the works done for the Software Verification and Validation, Software Safety Analysis, Software Quality Assurance, and Software Configuration Management etc.

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

External man-induced events in relation to nuclear power plant design. A Safety Guide. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

In order to take account of lessons learned since the first publication of the NUSS programme was issued, it was decided in 1986 to revise and reissue the Codes and Safety Guides. During the original development of these publications, as well as during the revision process, care was taken to ensure that all Member States, in particular those with active nuclear power programmes, could provide their input. Several independent reviews took place including a final one by the Nuclear Safety Standards Advisory Group (NUSSAG). The revised Codes were approved by the Board of Governors in June 1988. In the revision process new developments in technology and methods of analysis have been incorporated on the basis of international consensus. It is hoped that the revised Codes will be used, and that they will be accepted and respected by Member States as a basis for regulation of the safety of power reactors within the national legal and regulatory framework. 28 refs, 9 figs, 1 tab

Sports science needs more interdisciplinary, constraints-led research programmes: The case of water safety in New Zealand.

Science.gov (United States)

Button, C; Croft, J L

2017-12-01

In the lead article of this special issue, Paul Glazier proposes that Newell's constraints model has the potential to contribute to a grand unified theory of sports performance in that it can help to integrate the disciplinary silos that have typically operated in isolation in sports and exercise science. With a few caveats discussed in this commentary, we agree with Glazier's proposal. However, his ideas suggest that there is a need to demonstrate explicitly how such an integration might occur within applied scientific research. To help fill this perceived 'gap' and thereby illustrate the value of adopting a constraints-led approach, we offer an example of our own interdisciplinary research programme. We believe our research on water safety is ideally suited to this task due to the diverse range of interacting constraints present and as such provides a tangible example of how this approach can unify different disciplinary perspectives examining an important aspect of sport performance. Copyright © 2017 Elsevier B.V. All rights reserved.

GOSH! : an open and distance learning programme which helps in Gearing up to the Occupational Safety and Health Systems of the European Union

NARCIS (Netherlands)

Robertson, S.A.; Piek, W.S.M.; Kwantes, J.H.; Meeuwsen, J.M.; Man. M. de

1999-01-01

The GOSH! open and distance learning programme on the topic of occupational safety and health (OSH) was organized as part of the European Studies Programme. Prevention of damage to workers' health is an important issue in EU-policy. Apart from the individual human trauma, the socio-economic costs of

Design and implementation of a radiotherapy programme: Clinical, medical physics, radiation protection and safety aspects

International Nuclear Information System (INIS)

1998-09-01

It is widely acknowledged that the clinical aspects (diagnosis, decision, indication for treatment, follow-up) as well as the procedures related to the physical and technical aspects of patient treatment must be subjected to careful control and planning in order to ensure safe, high quality radiotherapy. Whilst it has long been recognized that the physical aspects of quality assurance in radiotherapy are vital to achieve and effective and safe treatment, it has been increasingly acknowledged only recently that a systematic approach is absolutely necessary to all steps within clinical and technical aspects of a radiotherapy programme as well. The need to establish general guidelines at the IAEA, taking into account clinical medical physics, radiation protection and safety considerations, for designing and implementing radiotherapy programmes in Member States has been identified through the Member States' increased interest in the efficient and safe application of radiation in health care. Several consultants and advisory group meetings were convened to prepare a report providing a basis for establishing a programme in radiotherapy. The present TECDOC is addressed to all professionals and administrators involved in the development, implementation and management of a radiotherapy programme in order to establish a common and consistent framework where all steps and procedures in radiotherapy are taken into account

Nuclear safety as applied to space power reactor systems

International Nuclear Information System (INIS)

Cummings, G.E.

1987-01-01

To develop a strategy for incorporating and demonstrating safety, it is necessary to enumerate the unique aspects of space power reactor systems from a safety standpoint. These features must be differentiated from terrestrial nuclear power plants so that our experience can be applied properly. Some ideas can then be developed on how safe designs can be achieved so that they are safe and perceived to be safe by the public. These ideas include operating only after achieving a stable orbit, developing an inherently safe design, ''designing'' in safety from the start and managing the system development (design) so that it is perceived safe. These and other ideas are explored further in this paper

Reactor Safety Analysis

International Nuclear Information System (INIS)

Arien, B.

2000-01-01

The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

Nuclear Safety Research Department annual report 2000

International Nuclear Information System (INIS)

Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E.

2001-08-01

The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

V and V methods of a safety-critical software for a programmable logic controller

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Yeol; Lee, Young Jun; Cha, Kyung Ho; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kong, Seung Ju [Korea Hydro and Nuclear Power Co., Ltd, Daejeon (Korea, Republic of)

2005-11-15

This paper addresses the Verification an Validation(V and V) process and the methodology for an embedded real time software of a safety-grade Programmable Logic Controller(PLC). This safety-grade PLC is being developed as one of the Korean Nuclear Instrumentation and Control System(KNICS) project KNICS projects are developing a Reactor Protection System(RPS) and an Engineered Safety Feature-Component Control System(ESF-CCS) as well as a safety-grade PLC. The safety-grade PLC will be a major component that encomposes the RPS systems and the ESF-CCS systems as nuclear instruments and control equipment. This paper describes the V and V guidelines an procedures, V and V environment, V and V process and methodology, and the V and V tools in the KNICS projects. Specifically, it describes the real-time operating system V and V experience which corresponds to the requirement analysis phase, design phase and the implementation and testing phase of the software development life cycle. Main activities of the V and V for the PLC system software are a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and a software configuration management. The proposed V and V methodology satisfies the Standard Review Plan(SRP)/Branch Technical Position(BTP)-14 criteria for the safety software in nuclear power plants. The proposed V and V methodology is going to be used to verify the upcoming software life cycle in the KNICS projects.

V and V methods of a safety-critical software for a programmable logic controller

International Nuclear Information System (INIS)

Kim, Jang Yeol; Lee, Young Jun; Cha, Kyung Ho; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon; Kong, Seung Ju

2005-01-01

This paper addresses the Verification an Validation(V and V) process and the methodology for an embedded real time software of a safety-grade Programmable Logic Controller(PLC). This safety-grade PLC is being developed as one of the Korean Nuclear Instrumentation and Control System(KNICS) project KNICS projects are developing a Reactor Protection System(RPS) and an Engineered Safety Feature-Component Control System(ESF-CCS) as well as a safety-grade PLC. The safety-grade PLC will be a major component that encomposes the RPS systems and the ESF-CCS systems as nuclear instruments and control equipment. This paper describes the V and V guidelines an procedures, V and V environment, V and V process and methodology, and the V and V tools in the KNICS projects. Specifically, it describes the real-time operating system V and V experience which corresponds to the requirement analysis phase, design phase and the implementation and testing phase of the software development life cycle. Main activities of the V and V for the PLC system software are a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and a software configuration management. The proposed V and V methodology satisfies the Standard Review Plan(SRP)/Branch Technical Position(BTP)-14 criteria for the safety software in nuclear power plants. The proposed V and V methodology is going to be used to verify the upcoming software life cycle in the KNICS projects

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-15

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

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

International Nuclear Information System (INIS)

Ualikhan Zhiyenbayev; Chung, Dae Wook

2015-01-01

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

Programmable logic controller (PLC) for safety systems of nuclear plants

International Nuclear Information System (INIS)

Sen, S.K.; Karmakar, G.; Joseph, Jose; Patil, R.K.

2002-01-01

Full text: A programmable logic controller (PLC) has been developed by RCnD, BARC for use in the safety critical systems in nuclear power plants. This PLC uses qualified hardware developed in RCnD for use in NPP. The programming software conforms to IEC-61131 part 3. The application programming is done on function block diagram (FBD) editor and the FBD is automatically converted into code in high level language (C / C++). This feature makes the application easily decipherable and therefore easily subjected to reviews and other validation techniques. The key to make quality software for use in nuclear systems is to enforce various standards in the design and development of the software, something, which is not possible to do with a commercially available PLC. This PLC with its software completely transparent lends itself to rigorous verification and validation easily

Safety issues and their ranking for WWER-440 model 213 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-04-01

The objective of this report is to present a consolidated list of generic safety concerns, called safety issues, ranked according to their safety significance and the corrective measures to improve safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. Section 2 provides and overview of the impact of all relevant issues on the main safety functions and other aspects important to overall plant safety. Section 3 presents safety issues identified in design according to the structure described below. Section 4 presents the safety issues in the area of operation, according to the same structure except that no ranking is given. At the end of Section 2, Tables 1 and 2 present a summary of all safety issues in a tabular form. 138 refs, tabs

Research plan on programmable automation systems in nuclear power plants (OHA) in 1995-1998

International Nuclear Information System (INIS)

Haapanen, P.; Pulkkinen, U.; Korhonen, J.

1995-05-01

The main purpose of nuclear energy research is to ensure the safety and continued development of Finnish nuclear power plants - a task which places high demands on expertise needed to support the work of public authorities and power companies. A factor necessarily influencing the orientation of the research is the Parliament's decision of late 1993 against further nuclear capacity in the country. Therefore the main emphasis of research shall be directed towards the ensuring the safety of existing plants and the continuous development of their safety along the progress of the science and technology. Anyhow, the preparedness for constructing new plants shall also be preserved. The utilization of programmable digital automation technology for the safety critical functions is the most significant change in the new plants, but also in existing plants this technology will be used for replacing and complementing the ageing automation systems. The safety evaluation of programmable digital systems can not be based on methods applied to conventional analog systems but new evaluation methods and tools must be developed for the assessing of their acceptability. (5 refs., 1 fig., 2 tabs.)

Diversity and testing requirements of programmable automation systems

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.

1993-04-01

In the report programmable digital operation and safety automation systems for nuclear power plants are discussed. The programmable systems deviate by their properties and behaviour from the conventional non-programmable systems in such extent, that their verification and validation for safety critical applications requires new methods and practices. The safety assessment can not be based on conventional probabilistic methods due to the difficulties in the quantification of the reliability of the software and hardware. A safety critical programmable system shall include diverse redundant parts so that no residual program fault can not cause the failure of the intended function of the system. Although complete testing of a programmable system is impossible, different tests have a central role in the production and validation process of the system. Diversity is important also in confidence building measures for the implemented system. Independent analysis and testing of the system should use different methods and tools from those used in the production and validation process by the system vendor. Use of diversity and testing are concluded to be central issues in producing safe programmable system and in proving them to be safe enough. By combining functional and programming diversity in a suitable way one can produce a system that is safe enough without having a non-programmable back-up system. (48 refs., 10 figs., 2 tabs.)

Possibilities and limitations of applying software reliability growth models to safety-critical software

International Nuclear Information System (INIS)

Kim, Man Cheol; Jang, Seung Cheol; Ha, Jae Joo

2007-01-01

It is generally known that software reliability growth models such as the Jelinski-Moranda model and the Goel-Okumoto's Non-Homogeneous Poisson Process (NHPP) model cannot be applied to safety-critical software due to a lack of software failure data. In this paper, by applying two of the most widely known software reliability growth models to sample software failure data, we demonstrate the possibility of using the software reliability growth models to prove the high reliability of safety-critical software. The high sensitivity of a piece of software's reliability to software failure data, as well as a lack of sufficient software failure data, is also identified as a possible limitation when applying the software reliability growth models to safety-critical software

The programme of the Minister of the Interior for technical regulations concerning the safety of nuclear facilities

International Nuclear Information System (INIS)

Berg, K.H.

1977-01-01

The BMI is responsible for the Atomic Energy Act being implemented. A survey is presented of the BMI's programme for setting up technical safety regulations (bar the KTA) according to the following categories: the structure of objects (hardware); the functions of machinery and human behaviour (software); know-how, abilities, responsibility of humans (live-ware); environment. (HP) [de

Regulatory review and confidence building in post-closure safety assessments and safety cases for near surface disposal facilities-IAEA ASAM coordinated research programme

International Nuclear Information System (INIS)

Gonzales, A.; Simeonov, G.; Bennett, D.G.; Nys, V.; Ben Belfadhel, M.

2005-01-01

Some years ago, the IAEA successfully concluded a Coordinated Research Program (CRP) called Islam, which focussed on the development of an Improved Safety Assessment Methodology for near-surface radioactive waste disposal facilities. In November 2002, and as an extension of ISAM, the IAEA launched a new CRP called ASAM, designed to test the Application of the Safety Assessment Methodology by considering a range of near-surface disposal facilities. The ASAM work programme is being implemented by three application working groups and two cross-cutting working groups. The application working groups are testing the applicability of the ISAM methodology by assessing an existing disposal facility in Hungary, a copper mine in South Africa, and a hypothetical facility containing heterogenous wastes, such as disused sealed sources. The first cross-cutting working group is addressing a number of technical issues that are common to all near-surface disposal facilities, while the second group, the Regulatory Review Working Group (RRWG) is developing guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides a brief overview of the work being conducted by the Regulatory Review Working Group. (author)

Extrabudgetary programme on the safety of nuclear installations in South East Asia Pacific and Far East countries. Report of the consultative meeting

International Nuclear Information System (INIS)

1997-07-01

Based on the good experience with the rapid expansion of nuclear utilization in Japan and South Korea, China is planning to significantly expand its nuclear programme, and other countries in the region are likely to follow this example in order to meet their expected high electricity demand growth. The building of NPPs is being considered in Indonesia, Malaysia, the Philippines, Thailand, and Vietnam. It is however recognized that countries in the region are in different stages of nuclear power programme, and that their needs for assistance in nuclear safety will be substantially different. In this situation it would be advantageous for all countries to establish regional co-operation on nuclear safety to learn from each other, use the experience accumulated in the world, and to commonly assess the progress made in nuclear safety matters. The objective of this Consultative Meeting was to discuss co-operation and the needs for assistance by Member States in South-East Asia, Pacific and Far East to strengthen the safety of their nuclear installations. Refs, figs, tabs

Overview and present status of the IAEA/RADWASS programme

International Nuclear Information System (INIS)

Abe, Masayoshi

1998-01-01

Since 1991 the International Atomic Energy Agency (IAEA) has been developing a series of safety standards documents in the field of radioactive waste management, named 'the Radioactive Waste Safety Standards (RADWASS) Programme'. The RADWASS programme is intended to establish and promote, in a coherent and comprehensive manner, the basic safety philosophy for radioactive waste management and the step necessary to ensure its implementation. And has main purposes that RADWASS publication will; (a) reflect the existing international consensus in the approaches and methodologies for a safe radioactive waste management, including disposal, and provide mechanisms to establish consensus where it does not yet exist; and (b) provide Member States with a comprehensive series of internationally agreed documents to assist in the derivation of and to complement national criteria, standards and practices. In progress, the programme was changed in 1996 its structure and documents preparation process as well as properties of RADWASS documents, the former phase was supervised by the International Radioactive Waste Management Advisory Committee (INWAC), and present phase is by the Waste Safety Standards Advisory Committee (WASSAC). Six safety series documents were published in the former programme, and several safety standards documents in the present RADWASS programme are in progress of publishing, some of them are expected to be published within several months. The overview and present status of the RADWASS programme including outline of those documents' contents already published and under the preparation are described in this report. (author)

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

International Nuclear Information System (INIS)

2012-01-01

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

Do clinical safety charts improve paramedic key performance indicator results? (A clinical improvement programme evaluation).

Science.gov (United States)

Ebbs, Phillip; Middleton, Paul M; Bonner, Ann; Loudfoot, Allan; Elliott, Peter

2012-07-01

Is the Clinical Safety Chart clinical improvement programme (CIP) effective at improving paramedic key performance indicator (KPI) results within the Ambulance Service of New South Wales? The CIP intervention area was compared with the non-intervention area in order to determine whether there was a statistically significant improvement in KPI results. The CIP was associated with a statistically significant improvement in paramedic KPI results within the intervention area. The strategies used within this CIP are recommended for further consideration.

Diversity for security: case assessment for FPGA-based safety-critical systems

Directory of Open Access Journals (Sweden)

Kharchenko Vyacheslav

2016-01-01

Full Text Available Industrial safety critical instrumentation and control systems (I&Cs are facing more with information (in general and cyber, in particular security threats and attacks. The application of programmable logic, first of all, field programmable gate arrays (FPGA in critical systems causes specific safety deficits. Security assessment techniques for such systems are based on heuristic knowledges and the expert judgment. Main challenge is how to take into account features of FPGA technology for safety critical I&Cs including systems in which are applied diversity approach to minimize risks of common cause failure. Such systems are called multi-version (MV systems. The goal of the paper is in description of the technique and tool for case-based security assessment of MV FPGA-based I&Cs.

Estimation of average hazardous-event-frequency for allocation of safety-integrity levels

International Nuclear Information System (INIS)

Misumi, Y.; Sato, Y.

1999-01-01

One of the fundamental concepts of the draft international standard, IEC 61508, is target failure measures to be allocated to Electric/Electronic/Programmable Electronic Safety-Related Systems, i.e. Safety Integrity Levels. The Safety Integrity Levels consist of four discrete probabilistic levels for specifying the safety integrity requirements or the safety functions to be allocated to Electric/Electronic/Programmable Electronic Safety-Related Systems. In order to select the Safety Integrity Levels the draft standard classifies Electric/Electronic/Programmable Electronic Safety-Related Systems into two modes of operation using demand frequencies only. It is not clear which modes of operation should be applied to Electric/Electronic/Programmable Electronic Safety-Related Systems taking into account the demand-state probability and the spurious demand frequency. It is essential for the allocation of Safety Integrity Levels that generic algorithms be derived by involving possible parameters, which make it possible to model the actuality of real systems. The present paper addresses this issue. First of all, the overall system including Electric/Electronic/programmable Electronic Safety-Related Systems is described using a simplified fault-tree. Then, the relationships among demands, demand-states and proof-tests are studied. Overall systems are classified into two groups: a non-demand-state-at-proof-test system which includes both repairable and non-repairable demand states and a constant-demand-frequency system. The new ideas such as a demand-state, spurious demand-state, mean time between detections, rates of d-failure and h-failure, and an h/d ratio are introduced in order to make the Safety Integrity Levels and modes of operation generic and comprehensive. Finally, the overall system is simplified and modeled by fault-trees using Priority-AND gates. At the same time the assumptions for modeling are described. Generic algorithms to estimate hazardous

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

Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-03-01

The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking. 73 refs, 3 tabs

Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1997-04-01

The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking

The radiation safety standards programme

International Nuclear Information System (INIS)

Bilbao, A.A.

2000-01-01

In this lecture the development of radiation safety standards by the IAEA which is a statutory function of the IAEA is presented. The latest editions of the basic safety standards published by the IAEA in cooperation with ICRP, FAO, ILO, NEA/OECD, PAHO and WHO are reviewed

Redox phenomena controlling systems - a 7. framework programme collaborative project (2008-2012)

International Nuclear Information System (INIS)

2013-01-01

The objective of this EURATOM collaborative project is to understand Redox phenomena controlling the long-term release/retention of radionuclides (ReCosy programme) in nuclear waste disposal and to provide tools to apply the results to safety assessment. The project has been organized into 6 task forces: 1) implications of Redox for safety, 2) development of Redox determination methods, 3) Redox response of defined and near-natural systems, 4) Redox reactions of radionuclides, 5) Redox processes in radionuclide transport, and 6) Redox reactions affecting the spent fuel source-term

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-09-01

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

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

International Nuclear Information System (INIS)

2000-09-01

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

[Organisational responsibility versus individual responsibility: safety culture? About the relationship between patient safety and medical malpractice law].

Science.gov (United States)

Hart, Dieter

2009-01-01

The contribution is concerned with the correlations between risk information, patient safety, responsibility and liability, in particular in terms of liability law. These correlations have an impact on safety culture in healthcare, which can be evaluated positively if--in addition to good quality of medical care--as many sources of error as possible can be identified, analysed, and minimised or eliminated by corresponding measures (safety or risk management). Liability influences the conduct of individuals and enterprises; safety is (probably) also a function of liability; this should also apply to safety culture. The standard of safety culture does not only depend on individual liability for damages, but first of all on strict enterprise liability (system responsibility) and its preventive effects. Patient safety through quality and risk management is therefore also an organisational programme of considerable relevance in terms of liability law.

Taking another look at the IAEA's OSART programme

International Nuclear Information System (INIS)

Franzen, F.L.

1990-01-01

The Operational Safety Review Team (OSART) programme of the International Atomic Energy Agency continues a high level of activity. In 1989 there were eleven OSART missions to nuclear power plants operating or approaching operation. The programme, now in its seventh year, has matured with its implementation. It reflects the principal change in operational safety that has occurred worldwide during these years: utilities operating nuclear power plants and industry organisations supporting the plants have become the spearhead in the international drive for excellence in operational safety. While this may reach beyond and supplement compliance with regulatory requirements, it also affects the IAEA's relation with regulatory authorities and utilities. Utilities have become the most important counterparts of the IAEA in implementing the OSART programme; in fact, the programme is now a special form of utility co-operation under the auspices of the IAEA. (author)

Seismic safety of nuclear power plants in Eastern Europe

International Nuclear Information System (INIS)

Gurpinar, A.; Godoy, A.

1995-01-01

This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in WWER type nuclear power plants during the past five years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on B enchmark study for the seismic analysis and testing of WWER type nuclear power plants . These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

Applying health education theory to patient safety programs: three case studies.

Science.gov (United States)

Gilkey, Melissa B; Earp, Jo Anne L; French, Elizabeth A

2008-04-01

Program planning for patient safety is challenging because intervention-oriented surveillance data are not yet widely available to those working in this nascent field. Even so, health educators are uniquely positioned to contribute to patient safety intervention efforts because their theoretical training provides them with a guide for designing and implementing prevention programs. This article demonstrates the utility of applying health education concepts from three prominent patient safety campaigns, including the concepts of risk perception, community participation, and social marketing. The application of these theoretical concepts to patient safety programs suggests that health educators possess a knowledge base and skill set highly relevant to patient safety and that their perspective should be increasingly brought to bear on the design and evaluation of interventions that aim to protect patients from preventable medical error.

The European fusion technology programme

International Nuclear Information System (INIS)

Goedkoop, J.A.

1984-01-01

With the 1982-86 pluriannual programme, reactor technology became a separate chapter in the fusion research programme of the European Commission. It comprises work on materials, the breeder blanket, tritium management, magnet coils, maintenance and the safety and environmental aspects. After an overview of the programme each of these areas is discussed briefly and some remarks are made on the role played by the European fission energy and magnet laboratories. (author)

Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

Energy Technology Data Exchange (ETDEWEB)

Lin, C.; Strupczewski, A. [International Atomic Energy Agency, Vienna (Austria)

1995-12-31

At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

Energy Technology Data Exchange (ETDEWEB)

Lin, C; Strupczewski, A [International Atomic Energy Agency, Vienna (Austria)

1996-12-31

At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

The IAEA Accident Management Programme

Energy Technology Data Exchange (ETDEWEB)

Kabanov, L.; Jankowski, M.; Mauersberger, H. (International Atomic Energy Agency, Vienna (Austria))

1993-02-01

Accident prevention and mitigation programmes and the Emergency Response System (ERS) are important elements of the Agency's activities in the area of nuclear power plant (NPP) safety. Safety Codes and Guides on siting, design, quality assurance and the operation of NPPs have been produced and are used by NPP operating organizations. Nuclear safety evaluation services are provided by the IAEA. The Emergency Response System and the International Nuclear Event Scale (INES) have been developed. The framework for the development of an accident management programme has been set up. The main goal is to develop an Accident Management Manual to provide a systematic, structured approach to the development and implementation of an accident management programme at NPPs. An outline of the Manual has been distributed and the first draft is available. The component parts are: Co-ordinated research programmes (CRPs) on severe accident management and containment behaviour; the use of vulnerability analysis; mitigation of the effects of hydrogen, and generic symptom oriented emergency operating procedures. The IAEA provides guidance by the dissemination of information on methods for accident management; collates information on approaches in this field in different organizations and countries; and arranges exchange of experience and the promulgation of knowledge through the training of NPP managers and senior technical staff. (orig.).

The IAEA Accident Management Programme

International Nuclear Information System (INIS)

Kabanov, L.; Jankowski, M.; Mauersberger, H.

1993-01-01

Accident prevention and mitigation programmes and the Emergency Response System (ERS) are important elements of the Agency's activities in the area of nuclear power plant (NPP) safety. Safety Codes and Guides on siting, design, quality assurance and the operation of NPPs have been produced and are used by NPP operating organizations. Nuclear safety evaluation services are provided by the IAEA. The Emergency Response System and the International Nuclear Event Scale (INES) have been developed. The framework for the development of an accident management programme has been set up. The main goal is to develop an Accident Management Manual to provide a systematic, structured approach to the development and implementation of an accident management programme at NPPs. An outline of the Manual has been distributed and the first draft is available. The component parts are: Co-ordinated research programmes (CRPs) on severe accident management and containment behaviour; the use of vulnerability analysis; mitigation of the effects of hydrogen, and generic symptom oriented emergency operating procedures. The IAEA provides guidance by the dissemination of information on methods for accident management; collates information on approaches in this field in different organizations and countries; and arranges exchange of experience and the promulgation of knowledge through the training of NPP managers and senior technical staff. (orig.)

Sign up to Safety: developing a safety improvement plan.

Science.gov (United States)

Dight, Carol; Peters, Hayley

2015-04-01

The Sign up to Safety (SutS) programme was launched in June 2014 by health secretary Jeremy Hunt. It focuses on listening to patients, carers and staff, learning from what they say when things go wrong, and then taking action to improve patient safety. The programme aims to make the NHS the safest healthcare system in the world by creating a culture devoted to continuous learning and improvement (NHS England 2014). Musgrove Park Hospital, part of Taunton and Somerset NHS Foundation Trust, was one of 12 NHS organisations that signed up to the SutS programme, making public its commitment to the national pledges to be 'open and transparent' and to develop a safety improvement plan. This paper describes the development of the strategy.

Reactor Safety Analysis

International Nuclear Information System (INIS)

Arien, B.

1998-01-01

The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

Applying the Trigger Review Method after a brief educational intervention: potential for teaching and improving safety in GP specialty training?

Science.gov (United States)

McKay, John; de Wet, Carl; Kelly, Moya; Bowie, Paul

2013-08-30

The Trigger Review Method (TRM) is a structured approach to screening clinical records for undetected patient safety incidents (PSIs) and identifying learning and improvement opportunities. In Scotland, TRM participation can inform GP appraisal and has been included as a core component of the national primary care patient safety programme that was launched in March 2013. However, the clinical workforce needs up-skilled and the potential of TRM in GP training has yet to be tested. Current TRM training utilizes a workplace face-to-face session by a GP expert, which is not feasible. A less costly, more sustainable educational intervention is necessary to build capability at scale. We aimed to determine the feasibility and impact of TRM and a related training intervention in GP training. We recruited 25 west of Scotland GP trainees to attend a 2-hour TRM workshop. Trainees then applied TRM to 25 clinical records and returned findings within 4-weeks. A follow-up feedback workshop was held. 21/25 trainees (84%) completed the task. 520 records yielded 80 undetected PSIs (15.4%). 36/80 were judged potentially preventable (45%) with 35/80 classified as causing moderate to severe harm (44%). Trainees described a range of potential learning and improvement plans. Training was positively received and appeared to be successful given these findings. TRM was valued as a safety improvement tool by most participants. This small study provides further evidence of TRM utility and how to teach it pragmatically. TRM is of potential value in GP patient safety curriculum delivery and preparing trainees for future safety improvement expectations.

Nuclear Safety Research Department annual report 2000

Energy Technology Data Exchange (ETDEWEB)

Majborn, B.; Damkjaer, A.; Nielsen, S.P.; Nonboel, E

2001-08-01

The report presents a summary of the work of the Nuclear Safety Research Department in 2000. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. In addition the department was responsible for the tasks 'Applied Health Physics and Emergency Preparedness', 'Dosimetry', 'Environmental Monitoring', and Irradiation and Isotope Services'. Lists of publications, committee memberships and staff members are included. (au)

What promotes sustainability in Safe Community programmes?

Science.gov (United States)

Nordqvist, Cecilia; Timpka, Toomas; Lindqvist, Kent

2009-01-08

The theory and practice of safety promotion has traditionally focused on the safety of individuals. This study also includes systems, environments, and organizations. Safety promotion programmes are designed to support community health initiatives taking a bottom-up approach. This is a long-term and complex process. The aim of this study was to try to empirically identify factors that promote sustainability in the structures of programmes that are managed and coordinated by the local government. Four focus group sessions with local government politicians and administrators in designated Safe Communities were conducted and analyzed using qualitative content analysis. Collaboration was found to be the basis for sustainability. Networks, enabling municipalities to exchange ideas, were reported to positively influence the programmes. Personal contacts rather than organizations themselves, determine whether collaboration is sustained. Participants reported an increase in cross-disciplinary collaboration among staff categories. Administrators and politicians were reported to collaborate well, which was perceived to speed up decision-making and thus to facilitate the programme work. Support from the politicians and the county council was seen as a prerequisite. Participants reported an increased willingness to share information between units, which, in their view, supports sustainability. A structure in which all local authorities' offices were located in close proximity to one another was considered to support collaboration. Appointing a public health coordinator responsible for the programme was seen as a way to strengthen the relational resources of the programme. With a public health coordinator, the 'external' negotiating power was concentrated in one person. Also, the 'internal' programme strength increased when the coordination was based on a bureaucratic function rather than on one individual. Increased relational resources facilitated the transfer of information

What promotes sustainability in Safe Community programmes?

Directory of Open Access Journals (Sweden)

Lindqvist Kent

2009-01-01

Full Text Available Abstract Background The theory and practice of safety promotion has traditionally focused on the safety of individuals. This study also includes systems, environments, and organizations. Safety promotion programmes are designed to support community health initiatives taking a bottom-up approach. This is a long-term and complex process. The aim of this study was to try to empirically identify factors that promote sustainability in the structures of programmes that are managed and coordinated by the local government. Methods Four focus group sessions with local government politicians and administrators in designated Safe Communities were conducted and analyzed using qualitative content analysis. Results Collaboration was found to be the basis for sustainability. Networks, enabling municipalities to exchange ideas, were reported to positively influence the programmes. Personal contacts rather than organizations themselves, determine whether collaboration is sustained. Participants reported an increase in cross-disciplinary collaboration among staff categories. Administrators and politicians were reported to collaborate well, which was perceived to speed up decision-making and thus to facilitate the programme work. Support from the politicians and the county council was seen as a prerequisite. Participants reported an increased willingness to share information between units, which, in their view, supports sustainability. A structure in which all local authorities' offices were located in close proximity to one another was considered to support collaboration. Appointing a public health coordinator responsible for the programme was seen as a way to strengthen the relational resources of the programme. Conclusion With a public health coordinator, the 'external' negotiating power was concentrated in one person. Also, the 'internal' programme strength increased when the coordination was based on a bureaucratic function rather than on one individual

The role of the public sector's research programme in support of the authorities and in building confidence on the safety of spent fuel disposal

International Nuclear Information System (INIS)

Vuori, S.; Rasilainen, K.

2002-01-01

A multiphase research programme was launched in 1989 to support the Finnish authorities in their activities concerning spent fuel management. The Finnish programme for spent fuel management has so far managed to keep its original time schedule at least partly due to clearly defined responsibilities between the nuclear energy producing industry and the authorities. It appears that the public sector's research programme has been successful in its supporting role by providing research results both on technical/ natural science and social science issues. In addition, the research programme has contributed directly and indirectly in building confidence on the post-closure and operational safety of a spent fuel disposal facility. (authors)

Applying different quality and safety models in healthcare improvement work: Boundary objects and system thinking

International Nuclear Information System (INIS)

Wiig, Siri; Robert, Glenn; Anderson, Janet E.; Pietikainen, Elina; Reiman, Teemu; Macchi, Luigi; Aase, Karina

2014-01-01

A number of theoretical models can be applied to help guide quality improvement and patient safety interventions in hospitals. However there are often significant differences between such models and, therefore, their potential contribution when applied in diverse contexts. The aim of this paper is to explore how two such models have been applied by hospitals to improve quality and safety. We describe and compare the models: (1) The Organizing for Quality (OQ) model, and (2) the Design for Integrated Safety Culture (DISC) model. We analyze the theoretical foundations of the models, and show, by using a retrospective comparative case study approach from two European hospitals, how these models have been applied to improve quality and safety. The analysis shows that differences appear in the theoretical foundations, practical approaches and applications of the models. Nevertheless, the case studies indicate that the choice between the OQ and DISC models is of less importance for guiding the practice of quality and safety improvement work, as they are both systemic and share some important characteristics. The main contribution of the models lay in their role as boundary objects directing attention towards organizational and systems thinking, culture, and collaboration

Public sector's research programme on nuclear waste management

International Nuclear Information System (INIS)

Vuori, S.

2000-06-01

According to the Finnish nuclear energy legislation, each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste as well as for the arising costs. Authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. In these tasks the authorities are supported by a research programme on nuclear waste management that is independent of the implementing organisations and power companies. The main objective of the research programme has been to provide the authorities with information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into the following main topic areas: (1) Behaviour of bedrock (2) Geohydrology and geochemistry, (3) Release of radionuclides from repository and subsequent transport in bedrock, (4) Engineered safety barriers of the repository, system, (5) Performance and safety assessment of spent fuel disposal facilities, (6) Waste management technology and costs (7) Evaluation of the contents and scope of and observation of the realisation of the environmental impact assessment procedure for the siting of spent nuclear fuel disposal facility, and research on other societal and sociopolitical issues, and (8) Public information, attitude, and image issues for waste management facilities. The research programme has generated considerably increased information on the behaviour of the natural and technical release barriers of the disposal system and thereby contributed to building of confidence on the long-term safety of geological disposal of spent fuel. Furthermore, increased confidence among the public in the affected candidate municipalities has probably been achieved by the complementary studies conducted within the research programme on topics

Status of the IAEA safety standards programme

International Nuclear Information System (INIS)

2002-01-01

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

Impact Assessment Road Safety Action Programme : assessment for mid term review : final report. Report on behalf of the European Commission, Directorate-General Energy and Transport.

NARCIS (Netherlands)

ECORYS Transport & SWOV Institute for Road Safety Research

2006-01-01

In 2003 the Commission published Saving 20000 lives on our roads, a shared responsibility, also known as the third European Road Safety Action Programme (RSAP). The RSAP describes concrete actions and proposals for actions by the Commission aimed at realising the target for improving road safety as

Overview on recent results of the VTT's research programme on assuring nuclear power plant structural safety

International Nuclear Information System (INIS)

Rintamaa, R.; Aaltonen, P.; Kauppinen, P.; Keinaenen, H.; Talja, H.; Valo, M.; Wallin, K.; Toerroenen, K.

1994-01-01

An overview of the Finnish national research programme on the Nuclear Power Plant Structural Safety, being carried out from 1990 to 1994, is presented. The focus of this paper is on recent results in the areas of experimental and computational fracture mechanics, material deterioration due to neutron irradiation, corrosion and water chemistry, nondestructive testing methods and procedures, and verification of structural integrity assessment methods by large scale component tests. (author). 21 refs, 21 figs, 2 tabs

The safety case for deep geological disposal of radioactive waste

International Nuclear Information System (INIS)

Kwong, Gloria

2014-01-01

The concept of a 'safety case' for a deep geological repository for radioactive waste was first introduced by the NEA Expert Group on Integrated Performance Assessment (IPAG). It was further developed in the NEA report entitled Confidence in the Long-term Safety of Deep Geological Repositories (1999), and since then it has been taken up in international safety standards as promulgated by the International Atomic Energy Agency (IAEA, 2006, 2011) and more recently in recommendations by the International Commission on Radiological Protection on the application of the system of radiological protection in geological disposal (ICRP, 2013). Many national radioactive waste disposal programmes and regulatory guides are also applying this concept. The NEA has used the safety case as a guide in several international peer reviews of national repository programmes and safety documentation. In Europe, the EU Directive 2011/70/ Euratom (EU, 2011) establishes a framework to ensure responsible and safe management of spent fuel and radioactive waste by member states that, inter alia, requires a decision-making process based on safety evidence and arguments that mirror the safety case concept. In 2007, the NEA, the IAEA and the European Commission (EC) organised a symposium on Safety Cases for the Deep Disposal of Radioactive Waste: Where Do We Stand? Since this time, however, there have been some major developments in a number of national geological disposal programmes and significant experience in preparing and reviewing cases for the operational and long-term safety of proposed and operating geological repositories. A symposium on The Safety Case for Deep Geological Disposal of Radioactive Waste: 2013 State of the Art was thus organised to assess developments since 2007 in the practice, understanding and roles of the safety case, as applied internationally at all stages of repository development, including the interplay of technical, regulatory and societal issues. The symposium

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

AN ADVANCED TOOL FOR APPLIED INTEGRATED SAFETY MANAGEMENT

Energy Technology Data Exchange (ETDEWEB)

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

2003-02-27

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

Outlook for the IAEA's technical co-operation programme

International Nuclear Information System (INIS)

Samiei, Massoud

1998-01-01

This is a slide presentation dealing with the following subjects: - the IAEA's programmes; - the technical co-operation programme; - past trends in the TC programme; - new initiatives in TC; - TC programme profile; - perspectives for the future. The major programmes conducted by IAEA are concerning: - nuclear power and fuel cycle; - nuclear applications; - nuclear, radiation and waste safety, nuclear verification and security material; - management of technical co-operation; - policy making, coordination and support. In relation with the IAEA role in development process the author presents the legal framework for TC, the programme structure, and programme areas, resources, budgets, cycle, approval and implementation. Two plots regarding the recipients with and without NPP's are displayed for the period 1980-1994. Also, according to the status of the member states (without and with nuclear power programme) the programme priorities are presented. For the first case these are: radiation and waste safety, food and agriculture, water resources management human health and nutrition, human resources development, environmental protection and industrial applications. For the second case there are mentioned: radiation and nuclear safety, nuclear power operation and maintenance management, radioactive waste management, environment protection and sustainable energy options. Concerning the regional distribution the following figures are given for 1997: West Asia, 9%; Europe, 18%; Inter-regional, 11%; Africa, 24%; Latin America, 21%; East Asia and Pacific, 17%. In conclusion, the hope is expressed that the value of Technical Co-operation Programme would be seen not only in the successful transfer of technology but also, in the way that the nuclear technologies may satisfy demands for sustainable development by having a lasting impact on the life of the majority in a cost effective and environmentally sound manner

The French-German initiative for Chernobyl. Programme 1 safety state of the sarcophagus

Energy Technology Data Exchange (ETDEWEB)

Pretzsch, G.; Roloff, R.; Roloff, R.; Artmann, A. [Gesellschaft fur Anlagenund Reaktorsicherheit (GRS) (Germany); Lhomme, V. [Institut de Radioprotection et de Surete Nucleaire, 92 - Fontenay-aux-Roses (France); Berberich, G. [Erftstadt-Gymnich (Germany); Selesnew, A

2005-07-01

The data collected and processed within the framework of the French-German Initiative are an excellent basis for the intended specialist application at the Chernobyl Centre as well as for an extended use in connection with the restoration of the Sarcophagus as part of the 'Shelter Implementation Plan' performed under the auspices of the European Bank for Reconstruction and Development. The major goals of the S.I.P. are the stabilisation of the existing Sarcophagus and the erection of a New Safe Confinement (N.S.C.) around the already existing Sarcophagus, the degasifier wing and the turbine building.This N.S.C. is to safely confine the radioactive materials for at least 100 years and is to allow their retrieval from inside if need be as well as the dismantling of the old structure.In addition, the database can be used for obtaining information needed for project descriptions, safety analysis reports, etc. The Ukrainian safety authority S.N.R.C.U. (State Nuclear Regulatory Committee of Ukraine) and its technical safety organisation, the State Scientific-Technical Center (S.S.T.C.), have also signaled their interest in using the database.Further information on the F.G.I. and on the 'Radioecology and Health Programmes' can be found at: www.fgi1-chernobyl.de.vu; www.grs.de, www.irsn.fr; www.fgi.icc.gov.ua. (N.C.)

Unique differences in applying safety analyses for a graphite moderated, channel reactor

International Nuclear Information System (INIS)

Moffitt, R.L.

1993-06-01

Unlike its predecessors, the N Reactor at the Hanford Site in Washington State was designed to produce electricity for civilian energy use as well as weapons-grade plutonium. This paper describes the major problems associated with applying safety analysis methodologies developed for commercial light water reactors (LWR) to a unique reactor like the N Reactor. The focus of the discussion is on non-applicable LWR safety standards and computer modeling/analytical variances of standards. The approaches used to resolve these problems to develop safety standards and limits for the N Reactor are described

Possibilities and Limitations of Applying Software Reliability Growth Models to Safety- Critical Software

International Nuclear Information System (INIS)

Kim, Man Cheol; Jang, Seung Cheol; Ha, Jae Joo

2006-01-01

As digital systems are gradually introduced to nuclear power plants (NPPs), the need of quantitatively analyzing the reliability of the digital systems is also increasing. Kang and Sung identified (1) software reliability, (2) common-cause failures (CCFs), and (3) fault coverage as the three most critical factors in the reliability analysis of digital systems. For the estimation of the safety-critical software (the software that is used in safety-critical digital systems), the use of Bayesian Belief Networks (BBNs) seems to be most widely used. The use of BBNs in reliability estimation of safety-critical software is basically a process of indirectly assigning a reliability based on various observed information and experts' opinions. When software testing results or software failure histories are available, we can use a process of directly estimating the reliability of the software using various software reliability growth models such as Jelinski- Moranda model and Goel-Okumoto's nonhomogeneous Poisson process (NHPP) model. Even though it is generally known that software reliability growth models cannot be applied to safety-critical software due to small number of expected failure data from the testing of safety-critical software, we try to find possibilities and corresponding limitations of applying software reliability growth models to safety critical software

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

Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-15

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Inspection of licensee - Maintenance programme and activities

International Nuclear Information System (INIS)

2013-01-01

An effective maintenance programme is critical to sustained safe and reliable operation of nuclear power plants. The Working Group on Inspection Practices (WGIP) concluded that when a licensee has an effective maintenance programme, the overall operating safety of the plant is improved and the protection of public health and safety enhanced. All Regulatory Bodies (RB) consider maintenance to be an important area for oversight. Although a variety of inspection practices are being used; RB are actively monitoring licensee performance. Specifically the following conclusions were reached and commendable practices identified: - Maintenance oversight by regulators appears to be in a stable continuous improvement state. Most regulators are executing inspection oversight based on an existing regulatory framework. - The performance of a licensee's maintenance programme is recognized as important part of maintaining nuclear safety. The result of the maintenance program assessment is included in the overall performance assessment of a license. - Maintenance inspection activities are recognized as an important part of the regulatory oversight process. Inspection activities are based on the safety significance and nature of work being performed by the licensee. - The effectiveness of the maintenance inspection activities is recognized to rely on properly qualified inspectors; who are adequately supported by specialists. Training and qualification of inspectors should be based on how the RB reviews and inspects licensee maintenance programmes. - Reporting requirements are identified to provide information on the licensees maintenance programme, and to help guide inspection activities. - Performance Indicators are recognized as a useful tool for helping focus regulatory activities. Basic PI are identified and tracked by the RB, and use of PI by the licensee is monitored. - Inspections are designed to confirm that the licensee is planning and scheduling maintenance with due

Diversity requirements for safety critical software-based automation systems

International Nuclear Information System (INIS)

Korhonen, J.; Pulkkinen, U.; Haapanen, P.

1998-03-01

System vendors nowadays propose software-based systems even for the most critical safety functions in nuclear power plants. Due to the nature and mechanisms of influence of software faults new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)' various safety assessment methods and tools for software based systems are developed and evaluated. This report first discusses the (common cause) failure mechanisms in software-based systems, then defines fault-tolerant system architectures to avoid common cause failures, then studies the various alternatives to apply diversity and their influence on system reliability. Finally, a method for the assessment of diversity is described. Other recently published reports in OHA-report series handles the statistical reliability assessment of software based (STUK-YTO-TR 119), usage models in reliability assessment of software-based systems (STUK-YTO-TR 128) and handling of programmable automation in plant PSA-studies (STUK-YTO-TR 129)

The deep geologic repository technology programme: toward a geoscience basis for understanding repository safety

International Nuclear Information System (INIS)

Jensen, M.R.

2007-01-01

Within the Deep Geologic Repository Technology Programme (DGRTP) several Geoscience activities are focused on advancing the understanding of groundwater flow system evolution and geochemical stability in a Canadian Shield setting as affected by long-term climate change. A key aspect is developing confidence in predictions of groundwater flow patterns and residence times as they relate to the safety of a deep geologic repository for used nuclear fuel waste. This is being achieved through a coordinated multi-disciplinary approach intent on: i) demonstrating coincidence between independent geo-scientific data; ii) improving the traceability of geo-scientific data and its interpretation within a conceptual descriptive model(s); iii) improving upon methods to assess and demonstrate robustness in flow domain prediction(s) given inherent flow domain uncertainties (i.e. spatial chemical/physical property distributions, boundary conditions) in time and space; and iv) improving awareness amongst geo-scientists as to the utility of various geo-scientific data in supporting a safety case for a deep geologic repository. This multi-disciplinary DGRTP approach is yielding an improved understanding of groundwater flow system evolution and stability in Canadian Shield settings that is further contributing to the geo-scientific basis for understanding and communicating aspects of DGR safety. (author)

IRSN safety research carried out for reviewing geological disposal safety case

International Nuclear Information System (INIS)

Serres, Christophe; Besnus, Francois; Gay, Didier

2010-01-01

The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

Reviewing industrial safety in nuclear power plants

International Nuclear Information System (INIS)

1990-02-01

This document contains guidance and reference materials for Operational Safety Review Team (OSART) experts, in addition to the OSART Guidelines (TECDOC-449), for use in the review of industrial safety activities at nuclear power plants. It sets out objectives for an excellent industrial safety programme, and suggests investigations which should be made in evaluating industrial safety programmes. The attributes of an excellent industrial safety programme are listed as examples for comparison. Practical hints for reviewing industrial safety are discussed, so that the necessary information can be obtained effectively through a review of documents and records, discussions with counterparts, and field observations. There are several annexes. These deal with major features of industrial safety programmes such as safety committees, reporting and investigation systems and first aid and medical facilities. They include some examples which are considered commendable. The document should be taken into account not only when reviewing management, organization and administration but also in the review of related areas, such as maintenance and operations, so that all aspects of industrial safety in an operating nuclear power plant are covered

School Area Road Safety Assessment and Improvements (SARSAI) programme reduces road traffic injuries among children in Tanzania.

Science.gov (United States)

Poswayo, Ayikai; Kalolo, Simon; Rabonovitz, Katheryn; Witte, Jeffrey; Guerrero, Alejandro

2018-05-19

To determine the impact of a paediatric road traffic injury (RTI) prevention programme in urban Sub-Saharan Africa. Dares Salaam, Republic of Tanzania. Household surveys were conducted in catchment areas around 18 primary schools in Dar es Salaam, Republic of Tanzania; the catchment areas were divided into control and intervention groups. Collected data included basic demographic information on all school-aged household members and whether or not they had been involved in an RTI in the previous 12 months, and, if so, what the characteristics of that RTI were. Based on these findings, a separate road safety engineering site analysis and consultation with the communities and other stakeholders, an injury-prevention programme was developed and implemented, consisting of infrastructure enhancements and a site-specific educational programme. The programme was initially implemented at the intervention schools. After 1 year, data were collected in the same manner. The control group received the same intervention after follow-up data were collected. Data were collected on 12 957 school-aged children in the baseline period and 13 555 school-aged children in the post-intervention period, in both the control and intervention communities. There was a statistically significant reduction in RTIs in the intervention group and a non-significant increase in RTI in the control group. The greatest reduction was in motorcycle-pedestrian RTI, private vehicle-pedestrian RTI and morning RTI. The programme demonstrated a significant reduction in paediatric RTI after its implementation, in very specific ways. This study demonstrates that for a reasonable investment, scientifically driven injury-prevention programmes are feasible in resource-limited settings with high paediatric RTI rates. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

The SCARABEE experimental fast reactor safety programme already completed

International Nuclear Information System (INIS)

Schmitt, A.P.; Teague, H.; Heusener, G.

1979-08-01

The SCARABEE in-pile experimental programme comprised a series of tests on unirradiated fuel pins, either single or in seven-pin clusters. The main objective was to obtain information on the mode and consequences of fast reactor fuel pin failure in conditions representative of loss of cooling in a LMFBR. The application of such programmes in full scale reactors leads to the great importance of the interpretation of experimental observations. The interpretation of that programme was carried out jointly by CEA, KFK and UKAEA; this international collaboration led to a sharper focusing on essential features to be modelled in experiments and computer codes and to a valuable convergence of views

The French nuclear programme

International Nuclear Information System (INIS)

Bacher, Pierre

1987-01-01

France has a civil nuclear power generation programme second only to the USA with 49 nuclear units in operation and 13 under construction. The units in service are described. These include 33 PWR 900 MW and 9 PWR 1300 MW units. The electricity consumption and generation in France is illustrated. The absence of a powerful anti-nuclear lobby and two main technical options have contributed to the success of the French nuclear programme. These are the PWR design and the plant standardization policy which allows the setting up of an effective industrial complex (eg for analysis of operating conditions and of safety and reliability information). The programme and the reasons for its success are reviewed. Research programmes and future plans are also discussed. (UK)

APPLIED FARM FOOD SAFETY

OpenAIRE

Ender, Judit; Mikaczo, Andrea

2008-01-01

Recently there have been more and more foodborne illnesses being associated with fresh vegetable produce. In response to this, consumer confidence has been lowered with the safety of the vegetable industry. So, many retailers have recently announced programs requiring growers to have independent third-party inspections. The goal with this essay is to introduce a vegetable farm and reveal its food safety procedures from the seeding through shipping,. reviewing, evaluating, and strengthening cu...

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

DEFF Research Database (Denmark)

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

2010-01-01

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

The safety of nuclear installations

International Nuclear Information System (INIS)

1993-01-01

This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

Safety requirements and safety experience of nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schnurer, H.L.

1977-01-01

Peaceful use of nuclear energy within the F.R.G. is rapidly growing. The Energy Programme of the Federal Government forecasts a capacity of up to 50.000 MW in 1985. Whereas most of this capacity will be of the LWR-Type, other activities are related to LMFBR - and HTGR - development, nuclear ships, and facilities of the nuclear fuel cycle. Safety of nuclear energy is the pacemaker for the realization of nuclear programmes and projects. Due to a very high population - and industrialisation density, safety has the priority before economical aspects. Safety requirements are therefore extremely stringent, which will be shown for the legal, the technical as well as for the organizational area. They apply for each nuclear facility, its site and the nuclear energy system as a whole. Regulatory procedures differ from many other countries, assigning executive power to state authorities, which are supervised by the Federal Government. Another particularity of the regulatory process is the large scope of involvement of independent experts within the licensing procedures. The developement of national safety requirements in different countries generates a necessity to collaborate and harmonize safety and radiation protection measures, at least for facilities in border areas, to adopt international standards and to assist nuclear developing countries. However, different nationally, regional or local situations might raise problems. Safety experience with nuclear facilities can be concluded from the positive construction and operation experience, including also a few accidents and incidents and the conclusions, which have been drawn for the respective factilities and others of similar design. Another tool for safety assessments will be risk analyses, which are under development by German experts. Final, a scope of future problems and developments shows, that safety of nuclear installations - which has reached a high performance - nevertheless imposes further tasks to be solved

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

International Nuclear Information System (INIS)

2007-04-01

This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

Categorization of Radioactive Sources. Safety Guide

International Nuclear Information System (INIS)

2009-01-01

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

Quality assurance for safety in nuclear power plants and other nuclear installations. Code and safety guides Q1-Q14. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The code provides the basic requirements for establishing and implementing quality assurance programmes for the stages of siting, design, construction, commissioning, operation and decommissioning of nuclear power plants. These basic requirements apply to all individuals and organizations, including designers, suppliers, constructors, manufacturers and operators. The basic quality assurance requirements presented in this Code also apply, with appropriate modifications, to nuclear installations other than nuclear power plants

Definition of the OPERA safety case for radioactive waste disposal in the Netherlands

International Nuclear Information System (INIS)

Hart, Jaap; Wildenborg, Ton; Davis, Paul; Becker, Dirk-Alexander; Verhoef, Ewoud

2014-01-01

framework for documenting and presenting all of the safety relevant information from the over 40 tasks in a consolidated manner. Central to the safety case lies the methodology of the probabilistic safety assessment. The proposed safety assessment structure is derived from the recent national and international efforts in order to include all relevant aspects deemed necessary and facilitates integration of the results of the different tasks in the safety assessment model environment. As OPERA builds on the ONDRAF/NIRAS disposal concept and research, focuses on the same geological formation on Boom Clay, collaboration is clearly advantageous for both parties. In the Belgian RD and D programme the concept of safety statements is being developed to manage information and focus the research to be relevant to support the safety case. To strengthen the collaboration between both RD and D programmes, this concept will be applied and further developed in OPERA as well. (authors)

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

CERN Document Server

Smith, David J

2010-01-01

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

The IAEA's high level radioactive waste management programme

International Nuclear Information System (INIS)

Saire, D.E.

1994-01-01

This paper presents the different activities that are performed under the International Atomic Energy Agency's (IAEA) high level radioactive waste management programme. The Agency's programme is composed of five main activities (information exchange, international safety standards, R ampersand D activities, advisory services and special projects) which are described in the paper. Special emphasis is placed on the RADioactive WAste Safety Standards (RADWASS) programme which was implemented in 1991 to document international consensus that exists on the safe management of radioactive waste. The paper also raises the question about the need for regional repositories to serve certain countries that do not have the resources or infrastructure to construct a national repository

Applying the trigger review method after a brief educational intervention: potential for teaching and improving safety in GP specialty training?

OpenAIRE

McKay, John; de Wet, Carl; Kelly, Moya; Bowie, Paul

2013-01-01

Background:\\ud The Trigger Review Method (TRM) is a structured approach to screening clinical records for undetected patient safety incidents (PSIs) and identifying learning and improvement opportunities. In Scotland, TRM participation can inform GP appraisal and has been included as a core component of the national primary care patient safety programme that was launched in March 2013. However, the clinical workforce needs up-skilled and the potential of TRM in GP training has yet to be teste...

NNP Life Management Programmes

International Nuclear Information System (INIS)

Hervia Ruperez, F.

1996-01-01

Around the world, power station owners are increasingly concerned to optimise Plant Life Management. In response, they are setting up Life Management programmes, of more or less ambitious scope and depth. Strategic, economic and security concerns and the close link between life extension work and the improved maintenance practices that are so important today, will increase and global these programmes for monitoring and conservation or mitigation of ageing. These programmes are all based on knowledge of the precise condition of all components and population with the greatest effect on the economics and safety of the plant, and trends in changes in their condition. (Author)

Developing a training programme for radiation protection officers at industrial irradiators

International Nuclear Information System (INIS)

Davor, P.

2013-04-01

A training programme for staff of irradiation facilities especially radiation safety officers at industrial irradiation facilities has been developed. The programme focused on technical and administrative basis for ensuring radiation safety at the practices. It consists of thirteen modules ranging from fundamentals of radiation, biological effects of ionizing radiation as well as the technical and administrative issues pertinent to radiation safety of the sources. The overall objective of this programme was to build competence in the area of radiation protection and raise the confidence level of staff of industrial irradiation facilities. The modules are structured in a manner that attempts to give a good understanding to participants on safety features of irradiators and use of radiation monitoring equipment. Each module has specific objectives and expected outcome and the course content is also stated under each module. The duration of the whole programme is sixteen weeks and the participants are expected to have some working knowledge in radiation protection and safe use of radiation sources. (au)

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

experience and harmonising safety approaches among Member States. However there is still a need to build on international cooperation in order to promote sharing of experience and knowledge for practical enhancement of nuclear safety. 3. Countries embarking on nuclear power programmes assume very important safety responsibilities that cannot and must not be delegated. Therefore, the establishment of a sustainable national safety infrastructure is an essential foundation for ensuring safe design, construction, operation and decommissioning of nuclear power plants. The process involves the development of a strong governmental, legal and regulatory framework as well as the necessary education and training, technical capacity building and integrated approach to safety, and safety management for all nuclear stakeholders. Vendor countries (vendors and regulators) that are supplying nuclear technology, materials and equipment to the new entrants have moral responsibility and common interest towards these countries and as such should contribute to the creation of strong safety infrastructures in the recipient countries. IAEA should support this process. Specific IAEA safety guides for countries embarking on nuclear power should be enhanced or developed and tailored safety reviews should be prerequisite at different stages of newcomer programme development. IAEA should also develop and provide to the newcomers appropriate training programmes to assure development of safety capacity. Other countries could also provide useful input particularly if they are involved in similar projects. 4. Operating Experience Feedback is an important element of the continuous safety improvement process for nuclear power plants. OEF databases should be analyzed and used more extensively and the lessons learned disseminated and applied among the Member States. All Member States, through their regulatory bodies, have the joint responsibility to adopt the OEF lessons learned in their respective nuclear

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

experience and harmonising safety approaches among Member States. However there is still a need to build on international cooperation in order to promote sharing of experience and knowledge for practical enhancement of nuclear safety. 3. Countries embarking on nuclear power programmes assume very important safety responsibilities that cannot and must not be delegated. Therefore, the establishment of a sustainable national safety infrastructure is an essential foundation for ensuring safe design, construction, operation and decommissioning of nuclear power plants. The process involves the development of a strong governmental, legal and regulatory framework as well as the necessary education and training, technical capacity building and integrated approach to safety, and safety management for all nuclear stakeholders. Vendor countries (vendors and regulators) that are supplying nuclear technology, materials and equipment to the new entrants have moral responsibility and common interest towards these countries and as such should contribute to the creation of strong safety infrastructures in the recipient countries. IAEA should support this process. Specific IAEA safety guides for countries embarking on nuclear power should be enhanced or developed and tailored safety reviews should be prerequisite at different stages of newcomer programme development. IAEA should also develop and provide to the newcomers appropriate training programmes to assure development of safety capacity. Other countries could also provide useful input particularly if they are involved in similar projects. 4. Operating Experience Feedback is an important element of the continuous safety improvement process for nuclear power plants. OEF databases should be analyzed and used more extensively and the lessons learned disseminated and applied among the Member States. All Member States, through their regulatory bodies, have the joint responsibility to adopt the OEF lessons learned in their respective nuclear

Safety management: a few techniques and their application

International Nuclear Information System (INIS)

Soundararajan, S.

2016-01-01

Industrial safety practice has grown in its stature tremendously since the age of industrial revolution. A number of modern techniques are available to strengthen design safety features, to review operational safety, and to critically appraise and upgrade practices of occupational safety and health management. This talk focuses on three prominent yet simple techniques and their usefulness in the overall safety management of a workplace. Any industrial set-up undergoes different stages in its life cycle-conceptual design, actual design, construction, fabrication and installation, commissioning, operation, shutdown/re-start up and decommissioning. Checklist procedure is a safety tool that can be applied at any of these stages. Thus it is a quite useful technique in safety management and accident prevention. It can serve as a form of approval from one step to another in the course of any routine or specific task. Safety Audit or Safety Review is a critical safety management appraisal tool. It gives a reasonable indication of how well a company's safety programme works, how hazards are recognised, how well employees are motivated and so on. It gives a clear picture about where a company stands as far as framing and implementation of its SHE policy is concerned. Each of the above tools is complementing each other and required to be applied at appropriate juncture in sustaining good safety management system at the workplace

SEAFP and SEAL: safety and environmental aspects

International Nuclear Information System (INIS)

Gulden, W.; Raeder, J.; Cook, I.

2000-01-01

The Safety and Environmental Assessment of Fusion Power (SEAFP) programme undertaken in the period 1992-1995 formed part of the ongoing effort in the European Fusion Programme to consider the safety and environmental aspects of fusion power. The assessment started with the development of a tokamak fusion power plant model of 3000 MW of fusion power. The analyses of safety included detailed consideration of effluents from normal operation, occupational doses, accidents (concentrating on the worst possible), and waste management. SEAFP was also the starting point for the Safety and Environmental Assessment of Fusion Power -- Long Term Programme (SEAL) initiated within the European Fusion Programme in 1995. SEAL aims at broadening the scope and elaborating selected aspects in more detail. SEAFP and SEAL confirmed the favourable safety and environmental characteristics of fusion power. They also confirmed the need to support these characteristics by dedicated materials development and safety-related design decisions. Recently, a new study on fusion safety (SEAFP-2) has been launched, defined for the time period 1997-1998, using SEAFP and SEAL findings as starting points

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

Safety assessment and verification for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

Nordic studies in reactor safety

International Nuclear Information System (INIS)

Pershagen, N.

1993-01-01

The Nordic Nuclear Safety Research Programme SIK programme in reactor safety is part of a major joint Nordic research effort in nuclear safety. The report summarizes the achievements of the SIK programme, which was carried out during 1990-1993 in collaboration between Nordic nuclear utilities, safety authorities, and research institutes. Three main projects were successfully completed dealing with: 1) development and application of a living PSA concept for monitoring the risk of core damage, and of safety indicators for early warning of possible safety problems; 2) review and intercomparison of severe accident codes, case studies of potential core melt accidents in nordic reactors, development of chemical models for the MAAP code, and outline of a system for computerized accident management support; 3) compilation of information about design and safety features of neighbouring reactors in Germany, Lithuania and Russia, and for naval reactors and nuclear submarines. The report reviews the state-of-the-art in each subject matter as an introduction to the individual project summaries. The main findings of each project are highlighted. The report also contains an overview of reactor safety research in the Nordic countries and a summary of fundamental reactor safety principles. (au) (69 refs.)

Establishing the quality assurance programme for a nuclear power plant project

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide provides requirements, recommendations and illustrative examples for establishing the overall quality assurance programme, and its constituent programmes, for a nuclear power plant project. It also provides guidance on the planning and documenting of programme plans and actions that are intended to ensure the achievement of the appropriate quality throughout the design, procurement, manufacture, construction, commissioning, operation and decommissioning of the nuclear power plant. The provisions of this Safety Guide are applicable to all organizations performing activities affecting the quality of items important to safety, such as designing, purchasing, fabricating, manufacturing, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling, modifying and decommissioning

Nuclear power and safety

International Nuclear Information System (INIS)

Chidambaram, R.

1992-01-01

Some aspects of safety of nuclear power with special reference to Indian nuclear power programme are discussed. India must develop technology to protect herself from the adverse economic impact arising out of the restrictive regime which is being created through globalization of safety and environmental issues. Though the studies done and experience gained so far have shown that the PHWR system adopted by India has a number of superior safety features, research work is needed in the field of operation and maintenance of reactors and also in the field of reactor life extension through delaying of ageing effects. Public relations work must be pursued to convince the public at large of the safety of nuclear power programme. The new reactor designs in the second stage of evolution are based on either further improvement of existing well-proven designs or adoptions of more innovative ideas based on physical principles to ensure a higher level of safety. The development of Indian nuclear power programme is characterised by a balanced approach in the matter of assuring safety. Safety enforcement is not just looked upon as a pure administrative matter, but experts with independent minds are also involved in safety related matters. (M.G.B.)

Regulatory practice for safety of nuclear energy in the German Democratic Republic

International Nuclear Information System (INIS)

Krueger, F.W.; Arndt, H.; Nessau, L.; Rabold, H.; Roehnsch, W.; Scheel, H.

1988-01-01

An outline of the regulatory practice applied in the GDR to ensure the safe use of nuclear energy is given in the form of answers to a questionnaire issued by the IAEA with the objective of giving the international community confidence in the safety of nuclear power programmes. (author)

Impact Assessment Road Safety Action Programme : assessment for mid term review : final report. Report on behalf of the European Commission, Directorate-General Energy and Transport.

OpenAIRE

ECORYS Transport & SWOV Institute for Road Safety Research

2006-01-01

In 2003 the Commission published Saving 20000 lives on our roads, a shared responsibility, also known as the third European Road Safety Action Programme (RSAP). The RSAP describes concrete actions and proposals for actions by the Commission aimed at realising the target for improving road safety as set in the White Paper (European Transport Policy for 2010: time to decide, 2001), namely halving the number of road deaths by 2010. Improving road safety in the EU is clearly a joint responsibilit...

The 7 basic tools of quality applied to radiological safety

International Nuclear Information System (INIS)

Gonzalez F, J.A.

1991-01-01

This work seeks to establish a series of correspondences among the search of the quality and the optimization of the doses received by the occupationally exposed personnel. There are treated about the seven basic statistic tools of the quality: the Pareto technique, Cause effect diagrams, Stratification, Verification sheet, Histograms, Dispersion diagrams and Graphics and control frames applied to the Radiological Safety

The IAEA programme on research reactor safety

International Nuclear Information System (INIS)

Abou Yehia, H.

2007-01-01

According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

The research group, the conference programme and academic training in safety promotion - a report of the activities at Karolinska Institutet, Sweden.

Science.gov (United States)

Hörte, Lars-Gunnar; Jansson, Bjarne; Svanström, Leif

2012-01-01

The research group was established in 1967 at Lund University and moved to Karolinska Institutet in 1980. Work began with epidemiological studies of all injuries in the local community in support of various experimental local interventions. An important element was the creation of 'surveillance systems' in healthcare. The work resulted in the establishment of a WHO Collaborating Centre and an international safety-building programme called 'Safe Communities'. In parallel, training at both master's and doctoral level and the building of a conference programme were embarked upon. The research group consists of three sections. Specific efforts are being made by some countries to address their own injury problems.

Development of quality assurance programme for prescribed ionizing radiation source testing. Recommendations

International Nuclear Information System (INIS)

1999-01-01

The document gives guidance to those applying for licence to perform ionizing radiation source acceptance tests and long-term stability tests and provides information which should be known when introducing quality assurance systems in compliance with legislative requirements. It is envisaged that this document ('Recommendations') will form a basis for final Safety Guides to be issued by the State Office for Nuclear Safety, the Czech nuclear regulatory authority. The setup of the publication is as follows. Part I gives a glossary of basic terms in quality systems. Part 2 explains quality system principles, paying special attention to radiation safety issues, and describes the structure and scope of quality system documentation. Part 3 explains the individual elements of the quality system and gives practical examples. Part 4 deals with the quality assurance programme; using instructions and practical examples, this part shows how the quality system elements should be applied to long-time stability testing and acceptance testing. A model structure of 2nd degree documentation (guidelines) and a model testing protocol are given in annexes. (P.A.)

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

A study on implementation of dynamic safety system in programmable logic controller for pressurized water reactor

International Nuclear Information System (INIS)

Kim, Ung Soo

1997-02-01

The dynamic safety system (DSS) is a computer based reactor protection system that has dynamic self-testing feature and fail-safe nature inherently. The inherent dynamic self-testing feature and fail-safe design provide a high level of reliability and low spurious trip rate. We can also reduce the time and human efforts to maintain the system by virtue of those features. Therefore, the application of the DSS to PWR has many advantages. The DSS has been applied only to advanced gas-cooled reactor (AGR) in the UK. In order to apply the DSS for PWR, the DSS has to be modified because there exist many differences between PWR and AGR for which the DSS was tested and installed. These differences are trip algorithms, monitored parameters, trip logics, and other conditions. In this study, the DSS algorithm is modified for PWR first. The modified DSS has several new features : 1) The modified DSS tests and processes time-dependent parameters, while the original DSS does not. 2) It has flexibility for handling several types of voting logic but the original DSS handles the only one type of voting - 2 out of 4 coincidence logic. Then, in this study, the modified DSS is implemented in programmable logic controller (PLC) using the ladder logic. Finally, the modified DSS is tested in two ways in this work : 1) The manual test is performed using direct input through the human computer interface (HCI) system. 2) The scenario based test is performed using input from the FISA-2/WS simulator. From the test results, it is shown that the modified DSS operates correctly in all conditions

20 CFR 645.260 - What health and safety provisions apply to participants in Welfare-to-Work programs?

Science.gov (United States)

2010-04-01

... Administrative Requirements § 645.260 What health and safety provisions apply to participants in Welfare-to-Work... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false What health and safety provisions apply to participants in Welfare-to-Work programs? 645.260 Section 645.260 Employees' Benefits EMPLOYMENT AND TRAINING...

Correcting Mortality for Loss to Follow-Up: A Nomogram Applied to Antiretroviral Treatment Programmes in Sub-Saharan Africa

Science.gov (United States)

Egger, Matthias; Spycher, Ben D.; Sidle, John; Weigel, Ralf; Geng, Elvin H.; Fox, Matthew P.; MacPhail, Patrick; van Cutsem, Gilles; Messou, Eugène; Wood, Robin; Nash, Denis; Pascoe, Margaret; Dickinson, Diana; Etard, Jean-François; McIntyre, James A.; Brinkhof, Martin W. G.

2011-01-01

Background The World Health Organization estimates that in sub-Saharan Africa about 4 million HIV-infected patients had started antiretroviral therapy (ART) by the end of 2008. Loss of patients to follow-up and care is an important problem for treatment programmes in this region. As mortality is high in these patients compared to patients remaining in care, ART programmes with high rates of loss to follow-up may substantially underestimate mortality of all patients starting ART. Methods and Findings We developed a nomogram to correct mortality estimates for loss to follow-up, based on the fact that mortality of all patients starting ART in a treatment programme is a weighted average of mortality among patients lost to follow-up and patients remaining in care. The nomogram gives a correction factor based on the percentage of patients lost to follow-up at a given point in time, and the estimated ratio of mortality between patients lost and not lost to follow-up. The mortality observed among patients retained in care is then multiplied by the correction factor to obtain an estimate of programme-level mortality that takes all deaths into account. A web calculator directly calculates the corrected, programme-level mortality with 95% confidence intervals (CIs). We applied the method to 11 ART programmes in sub-Saharan Africa. Patients retained in care had a mortality at 1 year of 1.4% to 12.0%; loss to follow-up ranged from 2.8% to 28.7%; and the correction factor from 1.2 to 8.0. The absolute difference between uncorrected and corrected mortality at 1 year ranged from 1.6% to 9.8%, and was above 5% in four programmes. The largest difference in mortality was in a programme with 28.7% of patients lost to follow-up at 1 year. Conclusions The amount of bias in mortality estimates can be large in ART programmes with substantial loss to follow-up. Programmes should routinely report mortality among patients retained in care and the proportion of patients lost. A simple

Strengthening leadership as a catalyst for enhanced patient safety culture

DEFF Research Database (Denmark)

Kristensen, Solvejg; Christensen, Karl Bang; Jaquet, Annette

2016-01-01

OBJECTIVES: Current literature emphasises that clinical leaders are in a position to enable a culture of safety, and that the safety culture is a performance mediator with the potential to influence patient outcomes. This paper aims to investigate staff's perceptions of patient safety culture...... in a Danish psychiatric department before and after a leadership intervention. METHODS: A repeated cross-sectional experimental study by design was applied. In 2 surveys, healthcare staff were asked about their perceptions of the patient safety culture using the 7 patient safety culture dimensions...... in the Safety Attitudes Questionnaire. To broaden knowledge and strengthen leadership skills, a multicomponent programme consisting of academic input, exercises, reflections and discussions, networking, and action learning was implemented among the clinical area level leaders. RESULTS: In total, 358 and 325...

Nuclear power plant ageing management programmes in foreign countries

International Nuclear Information System (INIS)

Simola, K.; Laakso, K.; Pekkonen, A.

1992-09-01

The report describes ageing studies of nuclear power plants and research programmes on plant life extension in foreign countries. Ageing studies are aimed to ascertain that the availability and safety of components and structures can be maintained throughout the plant lifetime. In life extension programmes the purpose is to evaluate the technical and economical possibilities to extend the plant lifetime beyond the originally planned operation period, without reducing the plant safety. The main emphasis of the report is put on the ageing and life extension programmes in the United States. Besides the U.S. studies, research on plant life extension possibilities conducted in France and Japan are also described. Examples of studies performed in other nuclear energy producing countries are given. These examples are mainly related to the development of maintenance programmes and techniques

IRSN safety research carried out for reviewing safety cases

International Nuclear Information System (INIS)

Serres, Ch.

2010-01-01

Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

Technical considerations for the development of an engineering safety features control system with PLC

International Nuclear Information System (INIS)

Lee, C. K.; Kim, C. H.; Han, J. B.; Kim, H.; Lee, S. S.

2002-01-01

Technical considerations are summarized for the development of an ESFCS(Engineered Safety Features Control System) with PLC (Programmable Logic Controller). The ESFCS is required for the mitigation of plant accident conditions and therefore developed in conformance with the design requirements applied to the safety critical system. The design of ESFCS primarily considered its safety, and the system has an architecture that will be able to minimize spurious actuation. The PLC based functional distribution and redundant design features are adopted, and the fieldbus is applied in the communication of information and control signals between PLC processors. It is expected that the ESFCS will have several advanced design features compared with the conventional systems supplied by foreign vendors

Safety of Nuclear Power Plants: Commissioning and Operation

International Nuclear Information System (INIS)

2011-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

A review of the HDR research programme

International Nuclear Information System (INIS)

Talja, H.; Koski, K.; Rintamaa, R.; Keskinen, R.

1995-10-01

In the German HDR (Heissdampfreaktor, hot steam reactor) reactor safety programme, experiments and simulating numerical analyses have been undertaken since 1976 to study the integrity and safety of light water reactors under operational and faulted conditions. The last experiments of the programme were conducted in 1991. The post test analyses have been finished by March 1994 and the last final reports were obtained a few months later. The report aims to inform the utilities and the regulatory body of Finland about the contents of the lokset HDR research programme and to consider the applicability of the results to safety analyses of Finnish nuclear power plants. The report centers around the thermal shock and piping component experiments within the last or third phase of the HDR programme. Investigations into severe reactor accidents, fire safety and non-destructive testing, also conducted during the third phase, are not considered. The report presents a review of the following experiment groups: E21 (crack growth under corrosive conditions, loading due to thermal stratification), E22 (leak rate and leak detection experiments of through-cracked piping), E23 (thermal transient and stratification experiments for a pipe nozzle), E31 (vibration of cracked piping due to blow down and closure of isolation valve), E32 (seismically induced vibrations of cracked piping), E33 (condensation phenomena in horizontal piping during emergency cooling). A comprehensive list of reference reports, received by VTT and containing a VTT more detailed description, is given for each experiment group. The review is focused on the loading conditions and their theoretical modelling. A comparison of theoretical and experimental results is presented for each experiment group. The safety margins are finally assessed with special reference to leak-before-break, a well known principle for assuring the integrity of primary circuit piping of nuclear power plants. (orig.) (71 figs., 5 tabs.)

Safety of the liquid-metal cooled fast breeder reactor and aspects of its fuel cycle

International Nuclear Information System (INIS)

Kessler, G.; Papp, R.; Huebel, D.

1977-01-01

Design and construction of the sodium-cooled fast reactors KNK-II (20MW(e)) and SNR-300 (300MW(e)) determine the status of safety engineering and safety R and D of LMFBRs in the Federal Republic of Germany. Both prototype fast power reactors have to go through a civil licensing process similar to that applied to present LWRs. A multilevel safety - or defence in depth - approach is applied to the design and construction of fast power reactors. All design data of the fast reactor plant are confirmed by extensive experimental programmes. Design limits of the plant are thoroughly discussed during the licensing process. Important safety R and D programmes have been and are still being performed. A very conservative safety analysis for hypothetical core and other plant accidents is used for present prototype fast reactors. The paper reviews the future trend of development of theoretical methods for accident analysis and the application of experimental results, especially in view of large commercial-type LMFBRs. The safety approach applied to the LMFBR plant is safe operation under normal operating conditions and safe shutdown under off-normal conditions. The consequences of releases of radioactivity to the environment meet the given standards. No chemical reprocessing plant for fast breeder fuel is in operation in the FRG at present; however, R and D work on investigation of all aspects and problem areas of the fast breeder fuel cycle are under way. Systems studies on safety aspects of the fast breeder fuel cycle (transport, reprocessing, fuel fabrication) and its impact on the environment have been performed and the main consequences of these studies are presented in the paper. (author)

Applied probabilistic methods in the field of reactor safety in Germany

International Nuclear Information System (INIS)

Heuser, F.W.

1982-01-01

Some aspects of applied reliability and risk analysis methods in nuclear safety and the present role of both in Germany, are discussed. First, some comments on the status and applications of reliability analysis are given. Second, some conclusions that can be drawn from previous work on the German Risk Study are summarized. (orig.)

Development of safety evaluation methods applied to the safety regulations for the operation stage of fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study is to establish the safety evaluation methods needed in the operation stage of fast breeder reactor (FBR). Related the above purpose of this study, some investigation studies for the technical standard applied to Monju were achieved in JFY 2012. (author)

Radiation protection programme for planned medical exposure situation

International Nuclear Information System (INIS)

Hanciles, Milford

2016-04-01

Radiation protection programme for planned medical exposure situation which involved diagnostic and interventional radiology was discussed. The radiation protection programme (RPP) should reflect the management’s commitment to radiation protection and safety through the management structure, policies, procedures and organizational arrangement commensurate with the nature and extent of the risk. Registrants and licensees should use the RPP as a tool for the development of a safety culture in diagnostic and interventional radiology departments .Recommendations are provided which when implemented in the education and training of radiographers, referral physician and all those involved in the use of ionizing radiation for diagnosis purposes will improve protection and safety of the occupationally exposed worker, the patient, the public and the environment. (au)

The Designing Bus for Nuclear Safety Class Controller

Energy Technology Data Exchange (ETDEWEB)

Lee, Dongil; Lee, Myeongkyun; Yun, Donghwa [PONUTech Co,. Ltd., Research Institute, Ulsan (Korea, Republic of); Ryoo, Kwangki [Hanbat National Univ., Daejeon (Korea, Republic of)

2013-10-15

EtherCAT (Ethernet for Control Automation Technology) is based on the IEEE 802.3 standard as one of the communication which is the I/O (Input/Output), sensors and communication function of PLC (Programmable Logic Controller) in industry and factory environment use is increasing. The Nuclear Safety Class Controller implemented by the EtherCAT applied bus can be shown the improving performance of data transmission in the controller.

The Designing Bus for Nuclear Safety Class Controller

International Nuclear Information System (INIS)

Lee, Dongil; Lee, Myeongkyun; Yun, Donghwa; Ryoo, Kwangki

2013-01-01

EtherCAT (Ethernet for Control Automation Technology) is based on the IEEE 802.3 standard as one of the communication which is the I/O (Input/Output), sensors and communication function of PLC (Programmable Logic Controller) in industry and factory environment use is increasing. The Nuclear Safety Class Controller implemented by the EtherCAT applied bus can be shown the improving performance of data transmission in the controller

Accident prevention programme

International Nuclear Information System (INIS)

1978-01-01

This study by the Steel Industry Safety and Health Commission was made within the context of the application by undertakings of the principles of accident and disease prevention previously adopted by the said Commission. It puts forward recommendations for the effective and gradual implementation of a programme of action on occupational health and safety in the various departments of an undertaking and in the undertaking as a whole. The methods proposed in this study are likely to be of interest to all undertakings in the metallurgical industry and other industrial sectors

Radiation protection programme for nuclear gauges

International Nuclear Information System (INIS)

Muzongomerwa, A.

2014-04-01

Ionizing radiation including the use of nuclear gauges can be very hazardous to humans and steps must be taken to minimize the risks so as to prevent deterministic effects and limiting chances for stochastic effects. The availability of a Radiation Protection Programme and its effective implementation ensures appropriate safety and security provisions for sealed radiation sources and promotes a safety culture within a facility that utilizes these sources. This study aims at establishing a guide on the radiation protection programme in nuclear gauges that comply with national requirements derived from current international recommendations. Elements that form part of a radiation protection programme are covered in detail as well as recommendations. The overall objective is to protect people (operators and the public) and the environment from the harmful effects of these sources if they are not properly controlled. Nuclear gauges for well logging and X-ray based gauges are outside the scope of this study. (au)

The performance regulatory approach in quality assurance: Its application to safety in nuclear power plants

International Nuclear Information System (INIS)

Sajaroff, Pedro M.

2000-01-01

In early 1991, the IAEA assembled an Advisory Group on the Comprehensive Revision of the Code and the Safety on Quality Assurance of the NUSS Programme. The Group was made up by specialists from a number of countries and from ISO, FORATOM, the EC and the IAEA itself, and its objective was completed in June 1995. This paper is aimed at describing the conceptual contents of the final draft of the revision 2 of the 50-C-QA Code 'Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Facilities' (hereinafter, the Code) which is essentially based on performance. Although the performance regulatory approach is not new in Argentina and in other countries, what is indeed novel is applying performance based QA. In such a way the Code will contribute to preventing both QA misinterpretations (i.e., a formalistic regulatory requirement) and the execution of non-effective work without attaining the needed quality level (what may be seen as a pathological deviation of QA). The Code contains ten basic requirements to be adopted when QA programmes are established and implemented in nuclear power plants. The goal is improving safety through an improvement in the methods applied for attaining quality. In line with the current developments in quality management techniques, priority is given to effectiveness of the QA programme. All the involved individuals (that is those in the managerial level, those performing the work and those assessing the work performed) must contribute to quality in a co-ordinated manner. The revised Safety Guides are being introduced, standing out those non existing before. Interrelation between quality assurance, safety culture and quality culture is to be noted. Besides QA for safety-related software mentioned as an issue to be considered by the IAEA. (author)

Building infrastructure for new nuclear power programmes

International Nuclear Information System (INIS)

Starz, A.; Aoki, M.

2010-01-01

In recent years, more than sixty countries have indicated that they are considering or launching nuclear power programmes. It has been more than a decade since a country commissioned its first nuclear power plant. In meantime, the global nuclear community has faced greater concerns about safety, security and non-proliferation, resulting in increased international obligations and a greater expectation for transparency and openness regarding nuclear power programmes. Many of these 'nuclear newcomers' are turning to International Atomic Energy Agency (IAEA) to understand the implications of the nuclear power option and to receive advice about how to proceed with implementing a national programme. In response to growing demand for assistance, the IAEA developed a comprehensive, phased approach to establishing the infrastructure necessary to support a national nuclear power programme. This 'Milestones' approach is described in Nuclear Energy Series Guide NG-G-3.1 'Milestones in the Development of a National Infrastructure for Nuclear Power' (2007). From establishing the national position and legal framework to nuclear safety, security and safeguards, the Milestones covers 19 issues that need to be addressed. This approach also places special emphasis on the need for involvement of the Government, utility, industry, academic, and other stakeholders in a national decision-making process. The IAEA is also helping 'newcomers' to better understand its Safety Standards, which were written from the perspective of operating nuclear power programmes. A new safety guide is in development which provides a Road-map to the safety standards and identifies the standards that are relevant for each phase consistent with the Milestones. Several countries in the Europe region are working with the IAEA to understand the issues associated with a nuclear power programme in preparation for making a knowledgeable commitment. The starting points and approaches vary widely: some are European

Framework for applying probabilistic safety analysis in nuclear regulation

International Nuclear Information System (INIS)

Dimitrijevic, V.B.

1997-01-01

The traditional regulatory framework has served well to assure the protection of public health and safety. It has been recognized, however, that in a few circumstances, this deterministic framework has lead to an extensive expenditure on matters hat have little to do with the safe and reliable operation of the plant. Developments of plant-specific PSA have offered a new and powerful analytical tool in the evaluation of the safety of the plant. Using PSA insights as an aid to decision making in the regulatory process is now known as 'risk-based' or 'risk-informed' regulation. Numerous activities in the U.S. nuclear industry are focusing on applying this new approach to modify regulatory requirements. In addition, other approaches to regulations are in the developmental phase and are being evaluated. One is based on the performance monitoring and results and it is known as performance-based regulation. The other, called the blended approach, combines traditional deterministic principles with PSA insights and performance results. (author)

Diversity and testing requirements of programmable automation systems; Ohjelmoitavan automaation diversiteetti- ja testausvaatimukset

Energy Technology Data Exchange (ETDEWEB)

Haapanen, P.; Maskuniitty, M.

1993-04-01

In the report programmable digital operation and safety automation systems for nuclear power plants are discussed. The programmable systems deviate by their properties and behaviour from the conventional non-programmable systems in such extent, that their verification and validation for safety critical applications requires new methods and practices. The safety assessment can not be based on conventional probabilistic methods due to the difficulties in the quantification of the reliability of the software and hardware. A safety critical programmable system shall include diverse redundant parts so that no residual program fault can not cause the failure of the intended function of the system. Although complete testing of a programmable system is impossible, different tests have a central role in the production and validation process of the system. Diversity is important also in confidence building measures for the implemented system. Independent analysis and testing of the system should use different methods and tools from those used in the production and validation process by the system vendor. Use of diversity and testing are concluded to be central issues in producing safe programmable system and in proving them to be safe enough. By combining functional and programming diversity in a suitable way one can produce a system that is safe enough without having a non-programmable back-up system. (48 refs., 10 figs., 2 tabs.).

Overview of OECD/NEA BEPU Programmes

International Nuclear Information System (INIS)

Amri, Abdallah; Gulliford, Jim; )

2013-01-01

The OECD/NEA paved the way for the development and assessment of BEPU for about 40 years, through concrete tasks: International Standard Problems (ISPs), Benchmarking activities, Development of Validation Matrices, Joint Safety Research Projects, and Specialist meetings. Several NEA related Best-Estimate Plus Uncertainties (BEPU) programmes have been successfully completed: Uncertainty Methods Study (UMS), Best-Estimate Methods - Uncertainty and Sensitivity Evaluation (BEMUSE), Safety Margin Assessment and Application (SM2A), Uncertainty Analysis in Modeling (UAM) Benchmark. New Programmes are underway to address pending issues (e.g., input uncertainties, uncertainties in coupled codes). The present Workshop may highlight new issues to be addressed (e.g., uncertainty analysis for CFD codes). Document available in the slides-form only

Publicly administrated nuclear waste management research programme 1994-1996. General plan for the research programme and research plan for 1994

International Nuclear Information System (INIS)

1994-01-01

The nuclear energy legislation of Finland includes detailed stipulations concerning nuclear waste management. Each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste, and for the financing of these operations. The authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. The principal goal of the JYT programme is to provide the authorities with information and research results relevant for the safety of nuclear waste management in order to support the various activities of the authorities. The whole field of the research programme is subdivided into the following main topic areas: (1) bedrock structure and stability, rock investigation methods, and characteristics and flow of groundwater, (2) release of radionuclides from a repository and subsequent migration in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management (4) natural analogue studies, (5) waste management technology and costs and (6) sociopolitical and other societal issues and environmental impact assessment

Programmable electronic system design & verification utilizing DFM

NARCIS (Netherlands)

Houtermans, M.J.M.; Apostolakis, G.E.; Brombacher, A.C.; Karydas, D.M.

2000-01-01

The objective of this paper is to demonstrate the use of the Dynamic Flowgraph Methodology (DIM) during the design and verification of programmable electronic safety-related systems. The safety system consists of hardware as well as software. This paper explains and demonstrates the use of DIM to

Safety functions and component classification for BWR, PWR and PTR

International Nuclear Information System (INIS)

1979-01-01

The Safety Guide forms part of the IAEA programme, referred to as the NUSS programme (Nuclear Safety Standards), for establishing Codes of Practice and Safety Guides relating to thermal neutron power plants. The present Safety Guide has the following chapters: safety functions, ranking of safety functions, assignment of safety class requirements. Design requirements for structural integrity of boundaries of fluid-retaining components are also discussed

Technology Programme

Energy Technology Data Exchange (ETDEWEB)

Batistoni, Paola; De Marco, Francesco; Pieroni, Leonardo [ed.

2005-07-01

The technology activities carried out by the Euratom-ENEA Association in the framework of the European Fusion Development Agreement concern the Next Step (International Thermonuclear Experimental Reactor - ITER), the Long-Term Programme (breeder blanket, materials, International Fusion Materials Irradiation Facility - IFMIF), Power Plant Conceptual Studies and Socio-Economic Studies. The Underlying Technology Programme was set up to complement the fusion activities as well to develop technologies with a wider range of interest. The Technology Programme mainly involves staff from the Frascati laboratories of the Fusion Technical and Scientific Unit and from the Brasimone laboratories of the Advanced Physics Technologies Unit. Other ENEA units also provide valuable contributions to the programme. ENEA is heavily engaged in component development/testing and in design and safety activities for the European Fusion Technology Programme. Although the work documented in the following covers a large range of topics that differ considerably because they concern the development of extremely complex systems, the high level of integration and coordination ensures the capability to cover the fusion system as a whole. In 2004 the most significant testing activities concerned the ITER primary beryllium-coated first wall. In the field of high-heat-flux components, an important achievement was the qualification of the process for depositing a copper liner on carbon fibre composite (CFC) hollow tiles. This new process, pre-brazed casting (PBC), allows the hot radial pressing (HRP) joining procedure to be used also for CFC-based armour monoblock divertor components. The PBC and HRP processes are candidates for the construction of the ITER divertor. In the materials field an important milestone was the commissioning of a new facility for chemical vapour infiltration/deposition, used for optimising silicon carbide composite (SiCf/SiC) components. Eight patents were deposited during 2004

Technology Programme

International Nuclear Information System (INIS)

Batistoni, Paola; De Marco, Francesco; Pieroni, Leonardo

2005-01-01

The technology activities carried out by the Euratom-ENEA Association in the framework of the European Fusion Development Agreement concern the Next Step (International Thermonuclear Experimental Reactor - ITER), the Long-Term Programme (breeder blanket, materials, International Fusion Materials Irradiation Facility - IFMIF), Power Plant Conceptual Studies and Socio-Economic Studies. The Underlying Technology Programme was set up to complement the fusion activities as well to develop technologies with a wider range of interest. The Technology Programme mainly involves staff from the Frascati laboratories of the Fusion Technical and Scientific Unit and from the Brasimone laboratories of the Advanced Physics Technologies Unit. Other ENEA units also provide valuable contributions to the programme. ENEA is heavily engaged in component development/testing and in design and safety activities for the European Fusion Technology Programme. Although the work documented in the following covers a large range of topics that differ considerably because they concern the development of extremely complex systems, the high level of integration and coordination ensures the capability to cover the fusion system as a whole. In 2004 the most significant testing activities concerned the ITER primary beryllium-coated first wall. In the field of high-heat-flux components, an important achievement was the qualification of the process for depositing a copper liner on carbon fibre composite (CFC) hollow tiles. This new process, pre-brazed casting (PBC), allows the hot radial pressing (HRP) joining procedure to be used also for CFC-based armour monoblock divertor components. The PBC and HRP processes are candidates for the construction of the ITER divertor. In the materials field an important milestone was the commissioning of a new facility for chemical vapour infiltration/deposition, used for optimising silicon carbide composite (SiCf/SiC) components. Eight patents were deposited during 2004

Technical self reliance of digital safety systems

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee Choon; Lee, Dong Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Kook Hun [Doosan Heavy Industries and Construction, Changwon (Korea, Republic of); Choi, Seung Gap [POSCON, Pohang (Korea, Republic of)

2009-04-15

This paper summarizes the development results of the Korea Nuclear Instrumentation and Control System (KNICS) project sponsored by the Korean government. In this project, Man Machine Interface System (MMIS) architecture, two digital platforms, and several control systems are developed. One platform is a programmable Logic Controller (PLC) for a safety system and another platform is a Distributed Control System (DCS) for a non safety system. With the POSAFE Q PLC, a Reactor Protection System (RPS) and an Engineered Safety Feature Component Control System (ESF CCS) are developed. A Power Control System (PCS) is developed based on the DCS. The safety grade platform and the digital safety systems obtained approval for the Topical Report from the Korean regulatory body in February of 2009. Also a Korean utility and a vendor company determined KNICS results to apply them to the planned Nuclear Power Plant (NPP) in March 2009. This paper introduces the technical self reliance experiences of the safety grade platform and the digital safety systems developed in the KNICS R and D project.

Experience with the use of programmable logic controllers in nuclear safety applications. Final report

International Nuclear Information System (INIS)

Brown, E.M.; Stofko, M.J.

1995-03-01

This report describes the implementation and experience with Programmable Logic Controllers (PLC) for nuclear safety applications. Two applications are described. The first is an Anticipated Transient Without Scram (ATWS) mitigation system provided as a Diverse Auxiliary Feedwater Actuation System (DAFAS). It was implemented at Arizona Public Service's Palo Verde Nuclear Generating Station and has been in commercial operation since early 1992. The second system described is an Emergency Diesel Generator Bus Load Sequencer installed at Florida Power and Light's Turkey Point Nuclear Power Plant. This system was installed as part of an upgrade to the emergency power system in 1988. The experience gained in the design, development, implementation and qualification of these systems will be beneficial to utilities that are considering the utilization of PLCs for their plant applications

Design for safety: theoretical framework of the safety aspect of BIM system to determine the safety index

Directory of Open Access Journals (Sweden)

Ai Lin Evelyn Teo

2016-12-01

Full Text Available Despite the safety improvement drive that has been implemented in the construction industry in Singapore for many years, the industry continues to report the highest number of workplace fatalities, compared to other industries. The purpose of this paper is to discuss the theoretical framework of the safety aspect of a proposed BIM System to determine a Safety Index. An online questionnaire survey was conducted to ascertain the current workplace safety and health situation in the construction industry and explore how BIM can be used to improve safety performance in the industry. A safety hazard library was developed based on the main contributors to fatal accidents in the construction industry, determined from the formal records and existing literature, and a series of discussions with representatives from the Workplace Safety and Health Institute (WSH Institute in Singapore. The results from the survey suggested that the majority of the firms have implemented the necessary policies, programmes and procedures on Workplace Safety and Health (WSH practices. However, BIM is still not widely applied or explored beyond the mandatory requirement that building plans should be submitted to the authorities for approval in BIM format. This paper presents a discussion of the safety aspect of the Intelligent Productivity and Safety System (IPASS developed in the study. IPASS is an intelligent system incorporating the buildable design concept, theory on the detection, prevention and control of hazards, and the Construction Safety Audit Scoring System (ConSASS. The system is based on the premise that safety should be considered at the design stage, and BIM can be an effective tool to facilitate the efforts to enhance safety performance. IPASS allows users to analyse and monitor key aspects of the safety performance of the project before the project starts and as the project progresses.

Formal model-based development for safety-critical embedded software

International Nuclear Information System (INIS)

Kim, Jin Hyun; Choi, Jin Young

2005-01-01

Safety-critical embedded software for nuclear I and C system is developed under the safety and reliability regulation. Programmable logic controller(PLC) is a computer system for instrumentation and control (I and C) system of nuclear power plants. PLC consists of various I and C logics in software, including real-time operating system (RTOS). Hence, errors related with RTOS should be detected and eliminated in development processes. Practically, the verification and validation for errors in RTOS is performed in test procedure, in which a lot of tasks for testing are embedded in RTOS and are running under a test environments. But the test process can not be enough to guarantee the safety and reliability of RTOS. Therefore, in this paper, we introduce to applying formal methods with the development of software for the PLC. We particularity apply formal methods to a development of RTOS for PLC, which is a safety critical level. In this development, we use the state charts of I-Logix to specify and verification and model checking to verify the specification

Formal model-based development for safety-critical embedded software

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Hyun; Choi, Jin Young [Korea University, seoul (Korea, Republic of)

2005-11-15

Safety-critical embedded software for nuclear I and C system is developed under the safety and reliability regulation. Programmable logic controller(PLC) is a computer system for instrumentation and control (I and C) system of nuclear power plants. PLC consists of various I and C logics in software, including real-time operating system (RTOS). Hence, errors related with RTOS should be detected and eliminated in development processes. Practically, the verification and validation for errors in RTOS is performed in test procedure, in which a lot of tasks for testing are embedded in RTOS and are running under a test environments. But the test process can not be enough to guarantee the safety and reliability of RTOS. Therefore, in this paper, we introduce to applying formal methods with the development of software for the PLC. We particularity apply formal methods to a development of RTOS for PLC, which is a safety critical level. In this development, we use the state charts of I-Logix to specify and verification and model checking to verify the specification.

Status of the BR2 refurbishment programme

International Nuclear Information System (INIS)

Koonen, E.

1995-01-01

The operation of the BR2 reactor with its second beryllium matrix is foreseen up to mid-1995. A refurbishment programme has been established in order to allow for future operation during at least ten years. Recently a positive decision to effectively carry out this programme has been taken. The refurbishment action plan follows from a general assessment of the different systems of BR2, with respect to their actual status, the operational experience and the evolution of safety standards and criteria. Ageing considerations were of uppermost importance in those assessments, not only to assure safety of future operation, but also to guarantee future availability and reliability. (orig.)

The safety culture change process performed in Polish research reactor MARIA

International Nuclear Information System (INIS)

Golab, Andrzej

2002-01-01

The Safety Culture Change Process Performed in research reactor MARIA is described in this paper. The essential issues fulfilled in realization of the Safety Culture Enhancement Programme are related to the attitude and behaviour of top management, co-operating groups, operational personnel, relations between the operating organization and the supervising and advising organizations. Realization of this programme is based on changing the employees understanding of safety, changing their attitudes and behaviours by means of adequate training, requalification process and performing the broad self-assessment programme. Also a high level Quality Assurance Programme helps in development of the Safety Culture. (author)

Safety cases for radioactive waste disposal facilities: guidance on confidence building and regulatory review IAEA-ASAM co-ordinated research project

International Nuclear Information System (INIS)

Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.

2008-01-01

The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)

EU research in 'operational safety of existing installations' under the nuclear fission programme 1998-2002

International Nuclear Information System (INIS)

Goethem, G. van; Zurita, A.; Manolatos, P.; Bermejo, J. Martin; Casalta, S.

2003-01-01

In this paper, an overview is given of the most important aspects of the research activities organised by the European Union (EU) in the area of reactor safety under the current 5th Euratom Framework Programme 1998-2002 (FP-5). This area is focussing on 'Operational Safety of Existing Installations'. The fundamental safety objective for nuclear power plants (NPPs) consists in protecting the public and the environment from the harmful effects resulting from ionising radiations. Community research with this objective is carried out through both 'indirect actions' (organised by DG Research) and 'direct actions' (carried out by DG Joint Research Centre/JRC). The mid-term achievements of this area were discussed at the symposium FISA-2001 (EC Luxembourg, 12-14 November 2001/750 pages, EUR 20281 EN, OPOCE Luxembourg 2002). This research area is actually part of the FP-5 Key Action NUCLEAR FISSION, which consists of the following four areas: reactor safety, waste management (including partitioning and transmutation), future systems (including high temperature reactors), and radiation protection. More specifically, this paper deals with the strategy, the organisation and the main achievements of the 73 multi-partner projects cosponsored by the European Union as 'indirect actions' (shared-cost and concerted actions). These projects are organised in three clusters, each devoted to one key safety issue. Each cluster is treated in a separate section of this paper, namely: (1) Plant Life Extension and Management (PLEM cluster), (2) Severe Accident Management (SAM cluster), and (3) Evolutionary Safety Concepts (EVOL cluster). The total cost of the 'indirect actions' of this Community research area is approximately Euro 82.5 million, out of which Euro 43 million is contributed by the EU budget. At FISA-2001, only the 'indirect actions' that started before 1 January 2001, were formally presented, i.e. a total of 41 projects - the 32 more recent multi-partner projects were

DS424: A Roadmap for the Implementation of the IAEA Safety Standards

International Nuclear Information System (INIS)

Yllera, Javier

2010-01-01

Many countries interested in developing nuclear power programmes for the first time need to have experience in using and regulating radioactive source materials. They need to have experience in building and operating large non-nuclear construction projects. Nuclear power has unique attributes and commitments associated with it that other industries do not. Although undertaken as a national endeavour with many national implications, building and operating a nuclear facility also has global implications (financial, political, safety, etc.). DG’s 2008 General Conference speech: “Every country has the right to introduce nuclear power, as well as the responsibility to do it right.”. The development of IAEA Safety Standards is an statutory function of the IAEA (article III of the IAEA Statute): “The Agency is authorized to establish or adopt… standards of safety for protection of health and minimization of danger to life and property…”. New guide (DS 424) constitutes a “Road-map” to apply the entire suite of IAEA Safety Standards progressively during the early phases of the implementation of a nuclear power programme. IAEA safety review missions based on internationally agreed safety standards are well established and are the best tools to build up confidence on the capacity of a country to develop nuclear energy in a safe way

Safety Training: scheduled sessions in September and October 2011

CERN Multimedia

DGS Unit

2011-01-01

The following training courses are scheduled in September – October. You can find the full Safety Training programme on the Safety Training online catalogue. If you are interested in attending any of the below courses, please talk to your supervisor, then apply electronically via EDH from the course description pages, by clicking on SIGN-UP. Registration for all courses is always open – sessions for the less-requested courses are organized on a demand-basis only. Depending on the demand, a session will be organised later in the year. Alphabetical order (original course titles are maintained) Chemical Safety – Introduction 11-OCT-11, 9.00 – 11.30, in English Conduite de chariots élévateurs 17-OCT-11 to 18-OCT-11, 8.00 – 17.30, in French * Ergonomics - Applying ergonomic principles in the workplace 15-SEP-11, 9.00 – 12.30, in French 15-SEP-11, 14.00 – 17.30, in English Habilitation électrique : Personne...

Environmental Modelling for Radiation Safety (EMRAS) - A Summary Report of the Results of the EMRAS Programme (2003-2007)

International Nuclear Information System (INIS)

2012-06-01

This publication provides a detailed overview of the results and achievements of the IAEA programme called EMRAS (Environmental Modelling for Radiation Safety), which ran from 2003 to 2007. The activities of the various working groups focused on the compilation of a handbook of parameter values for the prediction of radionuclide transfer in temperate environments, on the test and comparison of models to assess the transfer of tritium and 14C to biota and humans, on the validation of models for dose reconstruction due to 131I after the Chernobyl accident, on modelling the transfer of radionuclides in aquatic systems, on remediation of rural and urban sites with radioactive residues, and on the impact of environmental radioactivity on non-human species. The book concludes with a summary of the outcomes of the EMRAS programme and is accompanied by a CD-ROM which provides details of the work and the results of the working groups. (author)

Application of the WHO five keys of food safety to improve food ...

African Journals Online (AJOL)

Aim: To apply the WHO five keys of food safety in evidence based training programme for food vendors to improve the handling of street food. Methods: A total of 127 food vendors in Accra, the capital city of Ghana were sampled for interviews. Data collection from the vendors focused on (i) food handling practices (ii) ...

Mitigation of intergranular stress corrosion cracking in RBMK reactors. Final report of the programme's steering committee

International Nuclear Information System (INIS)

2002-09-01

In 2000 the IAEA initiated an Extrabudgetary Programme on Mitigation of Intergranular Stress Corrosion Cracking in RBMK Reactors to assist countries operating RBMK reactors in addressing the issue in austenitic stainless steel 300 mm diameter piping. Intergranular stress corrosion cracking of austenitic stainless steel piping in BWRs has been a major safety concern since the early seventies. Similar degradation was found in RBMK reactor piping in 1997. Early in 1998 the IAEA responded to requests for assistance from RBMK operating countries on this issue through activities organized in the framework of Technical Co-operation Department regional projects and the Extrabudgetary Programme on the Safety of WWER and RBMK Nuclear Power Plants. Results of these activities were a basis for the formulation of the objective and scope of the Extrabudgetary Programme on Mitigation of Intergranular Stress Corrosion Cracking in RBMK reactors ('the Programme'). The scope of the Programme included in-service inspection, assessment, repair and mitigation, and water chemistry and decontamination. The Programme was pursued by means of exchange of experience, formulation of guidance, transfer of technology, and training, which will assist the RBMK operators to address related safety concerns. The Programme implementation relied on voluntary extrabudgetary financial contributions from Japan, Spain, the United Kingdom and the USA, and on in kind contributions from Finland, Germany and Sweden. The Programme was implemented in close co-ordination with ongoing national and bilateral activities and major inputs to the Programme were provided through the activities of the Swedish International Project Nuclear Safety and of the US DOE International Nuclear Safety Program. The RBMK nuclear power plants in Lithuania, Russian Federation and Ukraine hosted most of the Programme activities. Support of these Member States involved in the Programme was instrumental for its successful completion in

The screening approach for review of accident management programmes

International Nuclear Information System (INIS)

Misak, J.

1999-01-01

In this lecture the screening approach for review of accident management programmes are presented. It contains objective trees for accident management: logic structure of the approach; objectives and safety functions for accident management; safety principles

Safety analysis of control rod drive computers

International Nuclear Information System (INIS)

Ehrenberger, W.; Rauch, G.; Schmeil, U.; Maertz, J.; Mainka, E.U.; Nordland, O.; Gloee, G.

1985-01-01

The analysis of the most significant user programmes revealed no errors in these programmes. The evaluation of approximately 82 cumulated years of operation demonstrated that the operating system of the control rod positioning processor has a reliability that is sufficiently good for the tasks this computer has to fulfil. Computers can be used for safety relevant tasks. The experience gained with the control rod positioning processor confirms that computers are not less reliable than conventional instrumentation and control system for comparable tasks. The examination and evaluation of computers for safety relevant tasks can be done with programme analysis or statistical evaluation of the operating experience. Programme analysis is recommended for seldom used and well structured programmes. For programmes with a long, cumulated operating time a statistical evaluation is more advisable. The effort for examination and evaluation is not greater than the corresponding effort for conventional instrumentation and control systems. This project has also revealed that, where it is technologically sensible, process controlling computers or microprocessors can be qualified for safety relevant tasks without undue effort. (orig./HP) [de

Program nuclear safety research: report 2000

International Nuclear Information System (INIS)

Muehl, B.

2001-09-01

The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2001. (orig.)

Topical session proceedings of the 4. IGSC meeting on: the potential impacts on repository safety from potential partitioning and transmutation programme

International Nuclear Information System (INIS)

Wollrath, Juergen; Voinis, Sylvie; Hadermann, Joerg; Van Luik, Abraham E.

2003-01-01

The bulk of radioactive waste results mainly from energy production in nuclear power plants. At present, this waste is safely stored near reactor sites, in dedicated storage facilities, and low-level wastes in some countries are disposed of in near surface disposal facilities. The stored wastes are accumulating, and the generally agreed-to solution is to dispose of vitrified waste or spent fuel in deep geological disposal facilities. The main concern in the disposal of radioactive waste is related to long-lived radionuclides - some of them will remain hazardous for tens of thousands of years and longer. To demonstrate the safety of geological disposal of radioactive waste a safety case has to be developed for a specific concept of disposal at a given site. This safety case is a collection of arguments at a given stage of repository development in support of the long-term safety of the repository. The safety case comprises the findings of a safety assessment and a statement of confidence in these findings. The type of waste to be disposed of is an important component of the disposal concept. At present, novel fuel cycles are under investigation at national and international levels including research in partitioning and transmutation (P and T) technologies. Comprehensive projects are carried out in OECD countries, notably France, Japan and the USA. Within the Nuclear Fission Safety programme the European Commission (EC) is supporting several projects and it is anticipated that the contribution of the EC will increase within the 6. Framework Programme. In addition the Nuclear Energy Agency has recently published a report comparing fuel cycles for accelerator driven systems and fast reactors. By using P and T it might be possible to reduce the long-lived component of the radioactive waste, thus easing the waste management problem. A safety case for a repository for wastes from P and T fuel cycles would be different from a safety case that deals with spent fuel and

RD and D steering of a geological disposal programme in poorly indurated clays

International Nuclear Information System (INIS)

Capouet, M.; Depaus, C.; Van Geet, M.; Lalieux, P.

2014-01-01

For more than thirty years, Belgium has been investigating clay formations for its potential suitability to host a geological disposal. The R and D programme initiated as early as 1974 by the Belgian Nuclear Research Centre (SCK.CEN) at Mol was pursued from the early 1980's under ONDRAF/NIRAS' responsibility. These studies quickly focused on the Boom Clay formation at Mol-Dessel, in north-eastern Belgium, as a potential host formation for a geological repository. The state of scientific and technical research on the possible disposal of high- and intermediate-level radioactive waste (B and C waste) in clay layers was presented in decennial safety assessment reports. The national and international peer review of the second Safety and Feasibility interim report SAFIR 2 acknowledged the maturity of the Belgian scientific programme and endorsed ONDRAF/NIRAS' conclusion to pursue the RD and D programme associated with a safe and feasible geological disposal in poorly indurated clays. Next to the continuing necessity of RD and D in all relevant areas of the Belgian programme, the NEA International Review Team (IRT) highlighted three main areas of activity that ONDRAF/NIRAS should strengthen to move on to the implementation phase. First, the IRT acknowledged the novel and innovative methodological concepts (i.e. safety functions, alternative safety indicators) introduced in its programme and recommended that ONDRAF/NIRAS move forward in this direction and improve the methodology for a more systematic, consistent and comprehensive treatment of uncertainties. Secondly, the IRT recommended further development of the EBS. Understanding of the engineered component's behaviour, its physic-chemical evolution with its inter-dependencies with the other components, its feasibility as well as its performance was indeed limited at the time of SAFIR 2. Last, the maturity of the geological programme suggested that it was time to initiate a dialogue with the regulators, policy makers

The Nordic programme for nuclear safety 1990-1993

International Nuclear Information System (INIS)

1992-02-01

The description of planned projects concerning nuclear safety is divided under the headings of readiness for action in situations of abnormal radiation, nuclear wastes and deposition, radioecology, and reactor safety - professional emergency-readiness. Coordination initiatives are also dealt with. In addition to this a survey of projects, coordinators and project leaders and a description of suggested new measures for nuclear safety are given. Under the first heading the subjects dealt with are spreading and local consequences, strategies, measuring methods and data exchange and management for decision-makers, evaluation, harmonization and effecting of plans, public information, a nordic emergency action exercise and reduction data connected with contaminated areas. The second heading covers criteria for classification of radioactive material, experiences in demolition of uranium-cleaning plants, information management, waste management in the case of field deposition with radioactivity from past reactor accidents and climatological and geological processes of significance for long-duration safety. Subjects under the third heading of radioecology cover training, quality assurance, aquatic radioecology, agricultural and natural ecosystems. Subjects under reactor safety include safety evaluation, the course of serious accidents, and data on neighbour-reactor system's conditions of safety. (AB)

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide (Russian Edition); Programma po vodno-khimicheskomu rezhimu dlya atomnykh ehlektrostantsij s vodookhlazhdaemymi reaktorami. Spetsial'noe rukovodstvo po bezopasnosti

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-02-15

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances.

The NKS-B Programme for Nordic cooperation on nuclear and radiological emergency preparedness, including measurement strategies, radioecology and waste management

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Leino, Kaisu; Magnússon, Sigurður M.

2014-01-01

The NKS platform for Nordic cooperation and competence maintenance in nuclear and radiological safety comprises two parallel programmes: the NKS-R programme on nuclear reactor safety and the NKS-B programme on emergency preparedness. This paper introduces the NKS-B programme and its current...

Latest developments on safety analysis methodologies at the Juzbado plant

International Nuclear Information System (INIS)

Zurron-Cifuentes, Oscar; Ortiz-Trujillo, Diego; Blanco-Fernandez, Luis A.

2010-01-01

Over the last few years the Juzbado Plant has developed and implemented several analysis methodologies to cope with specific issues regarding safety management. This paper describes the three most outstanding of them, so as to say, the Integrated Safety Analysis (ISA) project, the adaptation of the MARSSIM methodology for characterization surveys of radioactive contamination spots, and the programme for the Systematic Review of the Operational Conditions of the Safety Systems (SROCSS). Several reasons motivated the decision to implement such methodologies, such as Regulator requirements, operational experience and of course, the strong commitment of ENUSA to maintain the highest standards of nuclear industry on all the safety relevant activities. In this context, since 2004 ENUSA is undertaking the ISA project, which consists on a systematic examination of plant's processes, equipment, structures and personnel activities to ensure that all relevant hazards that could result in unacceptable consequences have been adequately evaluated and the appropriate protective measures have been identified. On the other hand and within the framework of a current programme to ensure the absence of radioactive contamination spots on unintended areas, the MARSSIM methodology is being applied as a tool to conduct the radiation surveys and investigation of potentially contaminated areas. Finally, the SROCSS programme was initiated earlier this year 2009 to assess the actual operating conditions of all the systems with safety relevance, aiming to identify either potential non-conformities or areas for improvement in order to ensure their high performance after years of operation. The following paragraphs describe the key points related to these three methodologies as well as an outline of the results obtained so far. (authors)

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

IAEA activities to prepare safety codes and guides for thermal neutron nuclear power plants

International Nuclear Information System (INIS)

Iansiti, E.

1977-01-01

programme is directed towards the safety of thermal nuclear power reactors; however, many of the documents can be very well applied to fast reactors. The first five codes have already completed the procedure and about ten to twelve safety guides will be ready in the course of 1977; the work will proceed then at the rate of about twelve safety guides a year, in the following years. On the basis of the experience gained in the preparation of these documents, and when a substantial part of the documents included in the programme of nuclear power plant safety have been published, it is foreseen that the programme be extended to include other nuclear facilities such as fabrication and reprocessing plants

OSART programme highlights 1995-1996. Operational safety practices in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States in enhancing the operational safety of nuclear power plants. This report continues the practice of summarizing mission results so that all the aspects of OSART missions, Pre-OSART missions and good practices are to be found in one volume. It also includes results of follow-up visits. Attempts have been made in this report to highlight the most significant findings whilst retaining as much of the vital background information as possible. This report is in four parts: Part I summarizes the most significant observations made during the missions and follow-up visits during 1995-1996; Part II, in chronological order, is an overview of the major strengths and opportunities for improvement identified during each OSART mission and summaries of follow-up visits performed during the period; Part III lists good practices that were identified during 1995 and 1996; and Part IV presents the OSART mission results (OSMIR) database. Each part of the report is intended for different levels in operating and regulatory organizations but not exclusively so. Part I is primarily to the executive management level; Part II to middle managers; and Parts III and IV to those involved in operational experience feedback. Because of widely different plant designs, operating and management styles, cultural practices, and other factors affecting plant operations, no OSART findings were applicable to all of the plants visited in 1995 and 1996. Individual findings varied considerably in scope and significance. However, the findings do reflect some common strengths and opportunities for improvement

Safety studies on oxide fuel elements for the fast neutron programme

International Nuclear Information System (INIS)

Ollier, H.; Truffert, J.

1976-01-01

Studies leading to the definition of a fuel element and instructions for its use overlap with safety studies to the extent that they must guarantee, for nominal running conditions, a failure rate consistent with the working rules of the Station. Given the present state of knowledge on the causes and kinetics of damage affecting the cladding, it is mainly dealt with the principles of this research. The advantages of applying statistical computing methods to the two factors which govern the lifetime of the pins: their working conditions and quality, are demonstrated [fr

National Programme for Radiological Protection in Medical Exposures

International Nuclear Information System (INIS)

2013-07-01

A national programme on radiation protection of patients can only be effective and sustainable if there is a joint effort between the regulatory body and the health authorities, and a cooperation with educational institutions, professional bodies and representatives of the industry. The regulatory body needs to promote a strategy of cooperation, and to identify obstacles that may prevent compliance with regulatory requirements and to address them. Not of least is the need for a continuous self-evaluation on the efficacy of the programme. Radiation safety of the patients is a responsibility of the users of the radiation sources involved in diagnostic and treatment. In particular, they are responsible for compliance with regulatory requirements. But safety depends also on aspects that are beyond the capabilities of those authorized to conduct practices. These aspects include educational programmes and institutions to implement them, calibration facilities, national protocols, professional bodies for the establishment of reference levels and contributions from the industry. Neither the users nor the regulatory body alone can achieve that these elements are in place. It needs a network of institutions and cooperation arrangements that involve educational and health authorities, laboratory facilities, professional bodies and the industry. A national programme has to include a strategy of cooperation, identification of obstacles that may prevent compliance with regulatory requirements and address them. Not of least is the need for a continuous self-evaluation on the efficacy of the programme. A group of regulatory agencies belonging to the Ibero American Forum of Nuclear and Radiation Regulatory Agency have exchanged experiences, lessons learned and good practices over three years. This exchange included extensive collaboration with the health authorities. The result of this work is this document containing a self-evaluation approach for the regulatory programme on

MRI safety of a programmable shunt assistant at 3 and 7 Tesla.

Science.gov (United States)

Mirzayan, M Javad; Klinge, Petra M; Samii, Madjid; Goetz, Friedrich; Krauss, Joachim K

2012-06-01

Several new shunt technologies have been developed to optimize hydrocephalus treatment within the past few years. Overdrainage, however, still remains an unresolved problem. One new technology which may reduce the frequency of this complication is the use of a programmable shunt assistant (proSA). Inactive in a horizontal position, it impedes CSF flow in a vertical position according to a prescribed pressure level ranging from 0 to 40 cm H(2)O. We exposed the proSA valve in an ex vivo protocol to MR systems operating at 3 and 7 Tesla to investigate its MRI safety. Following 3 Tesla exposure, no changes in valve settings were noted. Adjustment to any pressure level was possible thereafter. The mean deflection angle was 23 ± 3°. After exposure to 7 Tesla, however, there were unintended pressure changes, and the mechanism for further adjustment of the valves even disintegrated. According to the results of this study, proSA is safe with heteropolar vertical magnet alignment at 3 Tesla. Following 7 Tesla exposure, the valves lost their functional capability.

Status on the Finnish activities regarding qualification of programmable automation systems

International Nuclear Information System (INIS)

Juslin, K.

1995-01-01

The research work on qualification of programmable automation system is described which describe the development of methods, tools and practices for the evaluation and licensing of safety critical programmable automation systems. 26 refs

SUNflower +6 : a comparative study of the development of road safety in the SUNflower +6 countries : final report.

NARCIS (Netherlands)

Wegman, F.C.M. Eksler, V. Hayes, S. Lynam, D. Morsink, P. & Oppe, S. (eds.)

2006-01-01

This project has developed the SUNflower approach, originally used to assess Sweden, Great Britain and the Netherlands, for comparing safety programmes and records between countries. The approach has been applied to nine countries, adding three Central European countries (the Czech Republic, Hungary

Study programme on safety for environmental radioactivity during the period from 1986 to 1990

International Nuclear Information System (INIS)

1986-01-01

The study programme is divided into four topics. The first topic is a study on environmental doses, which was designed to identify levels of radioactivity, and characteristics and behavior of radiation sources in the ambient air, and to elucidate population dose estimates. The second topic concerning biological effects of radiation focusses on the elucidation for mechanism whereby radiation acts on the living body, for effects of low dose radiation using experimental animals, and for radiation effects on the human body using epidemiological approaches. The aim of the third topic is to study incorporation of alpha radiators, including transuranic elements, and tritium in the human body. The last topic is the safety evaluation, for which it is required to establish methods of evaluating human risk of environmental radiation and to prepare data base. An outline of these topics is given. (Namekawa, K.)

Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Ahmed, Ibrahim [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104 (Korea, Republic of); Jung, Jaecheon, E-mail: jcjung@kings.ac.kr [Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School, 658-91 Haemaji-ro, Seosang-myeon, Ulju-gun, Ulsan 45014 (Korea, Republic of); Heo, Gyunyoung [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104 (Korea, Republic of)

2017-06-15

Highlights: • An enhanced, systematic and integrated design verification approach is proposed for V&V of FPGA-based I&C system of NPP. • RPS bistable fixed setpoint trip algorithm is designed, analyzed, verified and discussed using the proposed approaches. • The application of integrated verification approach simultaneously verified the entire design modules. • The applicability of the proposed V&V facilitated the design verification processes. - Abstract: Safety-critical instrumentation and control (I&C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. However, safety analysis for FPGA-based I&C systems, and verification and validation (V&V) assessments still remain important issues to be resolved, which are now become a global research point of interests. In this work, we proposed a systematic design and verification strategies from start to ready-to-use in form of model-based approaches for FPGA-based reactor protection system (RPS) that can lead to the enhancement of the design verification and validation processes. The proposed methodology stages are requirement analysis, enhanced functional flow block diagram (EFFBD) models, finite state machine with data path (FSMD) models, hardware description language (HDL) code development, and design verifications. The design verification stage includes unit test – Very high speed integrated circuit Hardware Description Language (VHDL) test and modified condition decision coverage (MC/DC) test, module test – MATLAB/Simulink Co-simulation test, and integration test – FPGA hardware test beds. To prove the adequacy of the proposed

Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

International Nuclear Information System (INIS)

Ahmed, Ibrahim; Jung, Jaecheon; Heo, Gyunyoung

2017-01-01

Highlights: • An enhanced, systematic and integrated design verification approach is proposed for V&V of FPGA-based I&C system of NPP. • RPS bistable fixed setpoint trip algorithm is designed, analyzed, verified and discussed using the proposed approaches. • The application of integrated verification approach simultaneously verified the entire design modules. • The applicability of the proposed V&V facilitated the design verification processes. - Abstract: Safety-critical instrumentation and control (I&C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. However, safety analysis for FPGA-based I&C systems, and verification and validation (V&V) assessments still remain important issues to be resolved, which are now become a global research point of interests. In this work, we proposed a systematic design and verification strategies from start to ready-to-use in form of model-based approaches for FPGA-based reactor protection system (RPS) that can lead to the enhancement of the design verification and validation processes. The proposed methodology stages are requirement analysis, enhanced functional flow block diagram (EFFBD) models, finite state machine with data path (FSMD) models, hardware description language (HDL) code development, and design verifications. The design verification stage includes unit test – Very high speed integrated circuit Hardware Description Language (VHDL) test and modified condition decision coverage (MC/DC) test, module test – MATLAB/Simulink Co-simulation test, and integration test – FPGA hardware test beds. To prove the adequacy of the proposed

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

Implementation of an HACCP model in foot and mouth disease control programmes.

Science.gov (United States)

van Gelderen, C J; Durrieu, M; Schudel, A A

2015-12-01

The organisation and structure of the official Veterinary Services (OVS) are designed to meet a specific aim--the health certification of animal health, welfare and food safety in the production and processing stage. Disease prevention and control calls for programmes and projects that, depending on the characteristics of each disease, may involve any branch of the OVS, from the laboratory to field activities. For the purpose of this work, the model used is that of a country that is 'free from foot and mouth disease with vaccination' in accordance with the conditions stipulated in Chapter 8.8. of the World Organisation for Animal Health Terrestrial Animal Health Code. These conditions state that, to maintain this health status, a programme of monitoring and continuous control of the relevant variables must be implemented. This is achieved by applying good practice and identifying the critical control points in all processes, using a checklist that simplifies the task. The system that is developed can also serve as a guide for internal or external programme audits.

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition); Analisis determinista de seguridad para centrales nucleares. Guia de Seguridad Especifica

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

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

Safety of Nuclear Power Plants: Commissioning and Operation (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Safety of Nuclear Power Plants: Commissioning and Operation. Arabic Edition

International Nuclear Information System (INIS)

2011-01-01

This publication is a revision of Safety Requirements No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. It became necessary to revise the IAEA's safety requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Impact of early applied upper limb stimulation: The EXPLICIT-stroke programme design

Directory of Open Access Journals (Sweden)

Lindeman Eline

2008-12-01

Full Text Available Abstract Background Main claims of the literature are that functional recovery of the paretic upper limb is mainly defined within the first month post stroke and that rehabilitation services should preferably be applied intensively and in a task-oriented way within this particular time window. EXplaining PLastICITy after stroke (acronym EXPLICIT-stroke aims to explore the underlying mechanisms of post stroke upper limb recovery. Two randomized single blinded trials form the core of the programme, investigating the effects of early modified Constraint-Induced Movement Therapy (modified CIMT and EMG-triggered Neuro-Muscular Stimulation (EMG-NMS in patients with respectively a favourable or poor probability for recovery of dexterity. Methods/design 180 participants suffering from an acute, first-ever ischemic stroke will be recruited. Functional prognosis at the end of the first week post stroke is used to stratify patient into a poor prognosis group for upper limb recovery (N = 120, A2 project and a group with a favourable prognosis (N = 60, A1 project. Both groups will be randomized to an experimental arm receiving respectively modified CIMT (favourable prognosis or EMG-NMS (poor prognosis for 3 weeks or to a control arm receiving usual care. Primary outcome variable will be the Action Research Arm Test (ARAT, assessed at 1,2,3,4,5, 8, 12 and 26 weeks post stroke. To study the impact of modified CIMT or EMG-NMS on stroke recovery mechanisms i.e. neuroplasticity, compensatory movements and upper limb neuromechanics, 60 patients randomly selected from projects A1 and A2 will undergo TMS, kinematical and haptic robotic measurements within a repeated measurement design. Additionally, 30 patients from the A1 project will undergo fMRI at baseline, 5 and 26 weeks post stroke. Conclusion EXPLICIT stroke is a 5 year translational research programme which main aim is to investigate the effects of early applied intensive intervention for regaining dexterity

Detailed programme for research and development 1999-2004

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This report is a background to RD and D-Programme 98. The report gives an account of most of the research and development being conducted by SKB. The current state of knowledge is described, along with the goals and programmes that govern the continued work. The period of immediate concern comprises the next three years, 1999-2001. Chapters 2 and 3 give an account of the development of the safety assessment, and the methods and models used to assess long-term safety. Then follow a number of chapters that give an account of the R and D with primary purpose to support the safety assessment. There is also a description of some technical development of the deep repository and its components, as well as review of alternative methods such as partitioning and transmutation. Methods for investigation and evaluation of sites for the deep repository are also being further examined and developed, with sights set on the commencement of a site investigation by no earlier than 2001. A large part of SKBs research, development and demonstration is conducted in the form of projects. The majority of the projects have international participation. The Aespoe HRL (Hard Rock Laboratory) is an excellent example of this. A considerable portion of SKBs project-oriented R and D is concentrated to the Aespoe HRL. An important task for the Aespoe HRL is to test and demonstrate parts of the disposal system on a full scale. Finally, there is a chapter on scientific information. We want to communicate our scientific findings to the public and to local politicians and community leaders to obtain acceptance for a deep repository. It is the purpose of the safety assessment to develop and administer the methods and models for calculations employed by the safety assessment (Chapters 2 and 3). The topic-specific programmes serve to develop a better understanding of the processes dealt with in the safety assessment, to develop and review alternative models and to compile background data for the safety

Detailed programme for research and development 1999-2004

International Nuclear Information System (INIS)

1998-09-01

This report is a background to RD and D-Programme 98. The report gives an account of most of the research and development being conducted by SKB. The current state of knowledge is described, along with the goals and programmes that govern the continued work. The period of immediate concern comprises the next three years, 1999-2001. Chapters 2 and 3 give an account of the development of the safety assessment, and the methods and models used to assess long-term safety. Then follow a number of chapters that give an account of the R and D with primary purpose to support the safety assessment. There is also a description of some technical development of the deep repository and its components, as well as review of alternative methods such as partitioning and transmutation. Methods for investigation and evaluation of sites for the deep repository are also being further examined and developed, with sights set on the commencement of a site investigation by no earlier than 2001. A large part of SKBs research, development and demonstration is conducted in the form of projects. The majority of the projects have international participation. The Aespoe HRL (Hard Rock Laboratory) is an excellent example of this. A considerable portion of SKBs project-oriented R and D is concentrated to the Aespoe HRL. An important task for the Aespoe HRL is to test and demonstrate parts of the disposal system on a full scale. Finally, there is a chapter on scientific information. We want to communicate our scientific findings to the public and to local politicians and community leaders to obtain acceptance for a deep repository. It is the purpose of the safety assessment to develop and administer the methods and models for calculations employed by the safety assessment (Chapters 2 and 3). The topic-specific programmes serve to develop a better understanding of the processes dealt with in the safety assessment, to develop and review alternative models and to compile background data for the safety

Nuclear safety improvement activities related to WWER-440 units in Bulgaria

International Nuclear Information System (INIS)

Gantchev, T.

1998-01-01

The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

Plan of Nordic research in nuclear safety 1994-97

International Nuclear Information System (INIS)

1993-04-01

A new four-year Nordic research programme in the field of nuclear safety and radiation protection is to start in 1994 as a followup of several preceding Nordic programmes. It will include seven projects and a joint coordination function. The programme is intended to sustain a common understanding among safety authorities in the Nordic countries with respect to reactor safety and radiation protection. It mainly deals with questions that are actual within the Nordic region, but it may also include problems of concern to its eastern neighbours. Two of the projects deal with reactor safety, and one with radioactive waste. The other four projects are on environmental aspects: two of them deal with radioecology, and two with questions related to emergency preparedness. The programme is managed by the Nordic Committee for Safety Research, NKS, consisting of representatives from regulatory authorities, research bodies, and industry. Basic financing is provided by one consortium member from each of the five Nordic countries, whereby an annual budget of approximately 8 million Danish Kroner will be provided. Additional financing comes from sponsors interested in the programme as well as from those organizations taking part in the project work. Definite project plans are to be elaborated within the more general frames described in the present outline. The flexibility of the programme is enhanced by limiting the duration of individual activities to one or two years. This will make it possible to adjust the programme to actual needs in the Nordic countries. (au)

Development of Necessary Technology for localizing of Nuclear Safety Grade I and C System

International Nuclear Information System (INIS)

Kwon, Kee Choon; 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 and real time operating systems - The broadband communication network for safety information - Application of the automatic test for safety systems - Application of programmable logic controllers to nuclear plants - Development strategy for an integrated SW development tool for control device

Use of FPGA and CPLD in nuclear reactor safety systems and its regulatory review requirements for reactor safety

International Nuclear Information System (INIS)

Roy, Suvadip; Biswas, Animesh; Pradhan, S.K.

2015-01-01

Field Programmable Gate Arrays (FPGA) and Complex Programmable Logic Devices (CPLD) is being used widely in safety critical and safety related systems in nuclear power plans like in trip logic units, Engineered Safety Feature (ESF) actuation decision logic and neutronic signal processing for their reprogrammability feature and compact design. These HDL Programmable devices (HPD) are complex devices consisting of both hardware and software which is used to implement the logic on the FPGA. It is observed that these Programmable devices suffer from various modes of failure and the major failures in these devices are due to Single Event Upset (SEU), where a highly energetic ionizing radiation may lead to device failure which can even occur in radiologically benign environment. Other failures can occur during steps of developing the hardware using software tools like during Synthesis and placement and routing of the desired hardware. Here a study on use of such devices in Nuclear Reactors, study on mode of failures of these devices, way to tackle such failure and development of review guidelines for review of such devices used in safety critical and safety related systems with special emphasis on choice of software tools, way to mitigate effects of SEU and simulation and hardware testing results to be reviewed by regulatory body during design safety review is done. (author)

On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors

Energy Technology Data Exchange (ETDEWEB)

Sousa, A.L., E-mail: alsousa@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Ribeiro, A.C.O., E-mail: antonio.ribeiro@bayer.com [Bayer Crop Science Brasil S.A., Belford Roxo, RJ (Brazil); Duarte, J.P., E-mail: julianapduarte@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Departamento de Engenharia Nuclear; Frutuoso e Melo, P.F., E-mail: frutuoso@nuclear.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COOPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear

2013-07-01

Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)

On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors

International Nuclear Information System (INIS)

Sousa, A.L.; Ribeiro, A.C.O.; Duarte, J.P.; Frutuoso e Melo, P.F.

2013-01-01

Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)

OBTAINING FOOD SAFETY BY APPLYING HACCP SYSTEM

Directory of Open Access Journals (Sweden)

ION CRIVEANU

2012-01-01

Full Text Available In order to increase the confidence of the trading partners and consumers in the products which are sold on the market, enterprises producing food are required to implement the food safety system HACCP,a particularly useful system because the manufacturer is not able to fully control finished products . SR EN ISO 22000:2005 establishes requirements for a food safety management system where an organization in the food chain needs to proove its ability to control food safety hazards in order to ensure that food is safe at the time of human consumption. This paper presents the main steps which ensure food safety using the HACCP system, and SR EN ISO 20000:2005 requirements for food safety.

Best Practices in the Management of an Operating Experience Programme at Nuclear Power Plants

International Nuclear Information System (INIS)

2010-08-01

The IAEA Fundamental Safety Principles (IAEA Safety Standards Series No. SF-1) state the need for operating organizations to establish a programme for the feedback and analysis of operating experience in nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, lessons learned are disseminated to the staff of the organization and to the relevant national and international organizations and corrective actions are effectively implemented. In IAEA Operational Safety Review Team (OSART) and Peer Review of the effectiveness of the Operational Safety Performance Experience Review (PROSPER) missions, weaknesses in the management of operating experience (OE) programmes have been identified as one of the root causes of the recurrence of events. This publication has been developed to provide advice and assistance to nuclear installation managers and related institutions, including contractors and support organizations, to strengthen and enhance the management of their OE processes. In this publication, a number of barriers to the successful management of an OE programme have been identified. Managers are encouraged to review and evaluate these barriers with a view to identifying and eliminating them within their own organizations

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Guidance for the definition and application of probabilistic safety criteria

International Nuclear Information System (INIS)

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

2011-05-01

The project 'The Validity of Safety Goals' has been financed jointly by NKS (Nordic Nuclear Safety Research), SSM (Swedish Radiation Safety Authority) and the Swedish and Finnish nuclear utilities. The national financing went through NPSAG, the Nordic PSA Group (Swedish contributions) and SAFIR2010, the Finnish research programme on NPP safety (Finnish contributions). The project has been performed in four phases during 2006-2010. This guidance document aims at describing, on the basis of the work performed throughout the project, issues to consider when defining, applying and interpreting probabilistic safety criteria. Thus, the basic aim of the document is to serve as a checklist and toolbox for the definition and application of probabilistic safety criteria. The document describes the terminology and concepts involved, the levels of criteria and relations between these, how to define a probabilistic safety criterion, how to apply a probabilistic safety criterion, on what to apply the probabilistic safety criterion, and how to interpret the result of the application. The document specifically deals with what makes up a probabilistic safety criterion, i.e., the risk metric, the frequency criterion, the PSA used for assessing compliance and the application procedure for the criterion. It also discusses the concept of subsidiary criteria, i.e., different levels of safety goals. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications. (Author)

Guidance for the definition and application of probabilistic safety criteria

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.-E. (VTT Technical Research Centre of Finland (Finland)); Knochenhauer, M. (Scandpower AB (Sweden))

2011-05-15

The project 'The Validity of Safety Goals' has been financed jointly by NKS (Nordic Nuclear Safety Research), SSM (Swedish Radiation Safety Authority) and the Swedish and Finnish nuclear utilities. The national financing went through NPSAG, the Nordic PSA Group (Swedish contributions) and SAFIR2010, the Finnish research programme on NPP safety (Finnish contributions). The project has been performed in four phases during 2006-2010. This guidance document aims at describing, on the basis of the work performed throughout the project, issues to consider when defining, applying and interpreting probabilistic safety criteria. Thus, the basic aim of the document is to serve as a checklist and toolbox for the definition and application of probabilistic safety criteria. The document describes the terminology and concepts involved, the levels of criteria and relations between these, how to define a probabilistic safety criterion, how to apply a probabilistic safety criterion, on what to apply the probabilistic safety criterion, and how to interpret the result of the application. The document specifically deals with what makes up a probabilistic safety criterion, i.e., the risk metric, the frequency criterion, the PSA used for assessing compliance and the application procedure for the criterion. It also discusses the concept of subsidiary criteria, i.e., different levels of safety goals. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications. (Author)

International nuclear safety

International Nuclear Information System (INIS)

Wolff, P.H.W.

1978-01-01

The background to the development of internationally agreed safety principles and practices is discussed. The activities of the IAEA and the scope, structure, and organisation of its programme of Reactor Safety Codes and Guides are described. Attention is drawn to certain areas needing further considerations. (UK)

Radiation protection programme for uranium mining

International Nuclear Information System (INIS)

Mbeye, M.J.

2014-04-01

The Radiation Protection Programme (RPP) was developed to ensure that measures are in place for the occupational protection and safety in uranium mining facility. This work has established a number of protective measures that should be taken by the individual miners, licensee and all staff. It is not known whether Kayerekera Uranium mine has the technical and administrative capability for an effective radiation protection programme. The key in the mining facility is the control of dust through various means to prevent the escape of radon gas. Personal hygiene and local operating rules have been discovered to be very important for the protection and safety of the workers. The following components have also been discovered to be vital in ensuring safety culture in the mining facility: classification of working areas, monitoring of individuals and workplace, assignment of responsibilities, emergency preparedness, education and training and health surveillance. The regulatory body (Environmental Affairs Department of Malawi) should examine the major areas outlined in the RPP for Kayerekera uranium mine to find out the effectiveness of the RPP that is in place. (au)

Nuclear Safety Review for the Year 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-07-15

States with advanced nuclear power programmes to newcomer Member States or, on request, to those States that are expanding their nuclear power programmes. The Agency is actively involved in the development of safety goals for a robust and technically consistent framework for nuclear power plants and other nuclear and radiation installations and activities. This requires a holistic consideration of quantitative and qualitative criteria to ensure that no individual bears unacceptable radiation risks, as stated in the Agency's Fundamental Safety Principles (IAEA Safety Standards Series No. SF-1). Fuel cycle facilities, covering a diverse range of installations and processes - from mining to enrichment to fabrication to reprocessing to storage or disposal - present varying degrees of hazards and specific challenges to nuclear safety (e.g., criticality control, chemical hazards, fires and explosions). Events reported in 2010 to the Agency's Fuel Incident Notification and Analysis System (FINAS) indicated that the main root causes of these events were related to organizational and human factors. Of the 441 reactors currently operating around the world, many were built in the 1970s and 1980s, with an average lifespan of around 35 years. Their decommissioning peak will occur from 2020 to 2030 which will present a major managerial, technological, safety and environmental challenge to those States engaged in nuclear decommissioning. The need for national and international mechanisms for early planning, adequate funding and long term strategies applies not only to decommissioning, but also to radioactive waste management and spent fuel management, including disposal arrangements and clean-up, as well as the preservation of operational knowledge and experience to ensure the safety of these activities. Many of these issues were discussed in depth at the International Conference on Management of Spent Fuel from Nuclear Power Reactors held at the Agency in May, 2010. The collective

The role of underground laboratories in nuclear waste disposal programmes

International Nuclear Information System (INIS)

2001-01-01

Underground research laboratories (URLs) are essential to provide the scientific and technical information and practical experience that are needed for the design and construction of nuclear waste disposal facilities, as well as for the development of the safety case that must be presented at various stages of repository development. This report provides an overview of the purpose of URLs within repository development programmes; the range of URLs that have been developed, or are planned, in NEA Member countries to date; the various contributions that such facilities can make to repository development programmes and the development of a safety case; considerations on the timing of developing a URL within a national programme; and the opportunities and benefits of international co-operation in relation to URLs. (author)

Evaluation of safety practices and performance in a brewery industry ...

African Journals Online (AJOL)

Michael Horsfall

prevented in the period of the safety programme which translates to an average of 19.45 per year. The safety programme ... due to “weak safeguards against occupational and .... outputs within such a system. In this ..... Journal of Disaster Prevention and Management: ... Duignan, T. (2003), “Good health and safety is good.

Independent V and V for Safety Grade I and C System

International Nuclear Information System (INIS)

Lee, Jang Soo; Kwon, Kee Choon; Lee, Dong Young

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 real time operating system for safety-grade computers - V and V of the broadband communication network for safety information - Independent V and V for application of programmable logic controllers to nuclear plants - Development strategy for an integrated SW development tool for control devices

The Safety Assessment of OPR-1000 for Station Blackout Applying Combined Deterministic and Probabilistic Procedure

Energy Technology Data Exchange (ETDEWEB)

Kang, Dong Gu; Ahn, Seung-Hoon; Cho, Dae-Hyung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

This is termed station blackout (SBO). However, it does not generally include the loss of available AC power to safety buses fed by station batteries through inverters or by alternate AC sources. Historically, risk analysis results have indicated that SBO was a significant contributor to overall core damage frequency. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident, which is a typical beyond design basis accident and important contributor to overall plant risk, is performed by applying the combined deterministic and probabilistic procedure (CDPP). In addition, discussions are made for reevaluation of SBO risk at OPR-1000 by eliminating excessive conservatism in existing PSA. The safety assessment of OPR-1000 for SBO accident, which is a typical BDBA and significant contributor to overall plant risk, was performed by applying the combined deterministic and probabilistic procedure. However, the reference analysis showed that the CDF and CCDP did not meet the acceptable risk, and it was confirmed that the SBO risk should be reevaluated. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it was demonstrated that the proposed CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

Recent state report: Groundwater programmes of variable density

International Nuclear Information System (INIS)

Fein, E.

1991-12-01

This report summarises basic facts and data that may be helpful in decisions about the development of a groundwater programme for the calculation of saline groundwater movements. Generally accepted requirements of a rapid groundwater programme for the assessment of flow mechanisms above salt domes are defined. It also describes the possibilities offered by similar programmes already in progress on a national and international basis and discusses state-of-the-art numerical methods and hardware in respect of speed and efficiency of the relevant computer programmes. The availability of a rapid groundwater programme would make it possible for model calculations in connection with long-term safety analyses to take account of the influence of salinity on groundwater movements in extended and complex model regions. (orig./DG) [de

Synthesis report of a reactor-physics programme devoted to the qualification of the project calculation methods applied to the mixed (U-Pu) fuelled reloadings

International Nuclear Information System (INIS)

Golinelli, C.

1982-01-01

The Commission of the European Communities has sponsored three sets of experiments with a contract in the framework of the LWR plutonium recycling programme. The aim of this experimental programme was to supplement the qualification of the computer codes used in connection with control and safety studies relating to plutonium recycling in LWR power stations. The experiments are performed at the Cadarache centre by CEA and EdF in the MINERVE and EOLE facilities. The power distributions in various kinds of assemblies with some heterogeneities (water holes, absorbers, UO 2 /UO 2 -PuO 2 interfaces) are studied in MINERVE as well as the DOPPLER effect. This second programme consisted in oscillating the UO 2 and UO 2 -PuO 2 samples which were heated between 20 0 C and 800 0 C. The CREOLE experiments in EOLE dealt with the moderator temperature effect from 20 0 C to 300 0 C. All the results show that the calculation schema for the hot point values must be sophisticated and that it is possible to reduce the uncertainties concerning the feedback factors

Quality control programme for radiotherapy

International Nuclear Information System (INIS)

Campos de Araujo, A.M.; Viegas, C.C.B.; Viamonte, A.M.

2002-01-01

A 3 years pilot programme started in January 2000 with 33 philanthropic cancer institutions that provides medical services to 60% of the patients from the national social security system. Brazil has today 161 radiotherapy services (144 operating with megavoltage equipment). These 33 institutions are distributed over 19 Brazilian states. The aim of this programme is: To create conditions to allow the participants to apply the radiotherapy with quality and efficacy; To promote up dating courses for the physicians, physicists and technicians of these 33 Institutions. With the following objectives: To recommend dosimetric and radiological protection procedures in order to guarantee the tumor prescribed dose and safe working conditions; To help in establishing and implementing these procedures. The main activities are: local quality control evaluations, postal TLD audits in reference conditions, postal TLD audits in off axis conditions and training. The local quality control program has already evaluated 22 institutions with 43 machines (25 Co-60 and 18 linear accelerators). In these visits we perform dosimetric, electrical, mechanical and safety tests. As foreseen, we found more problems among the old Co-60 machines i.e., field flatness, size, symmetry and relative output factors; lasers positioning system alignment; optical distance indicator; radiation and light field coincidence; optical and mechanical distance indicators agreement, than among the linear accelerators i.e., field flatness and size; lasers positioning system alignment; tray interlocking and wedge filter factors

Results of research into nuclear power plant safety

International Nuclear Information System (INIS)

Polak, V.; Hladky, E.; Moravek, J.; Suchomel, J.; Stehlik, J.

1976-01-01

A survey is given of computer programmes for the safety analysis of nuclear power plants with WWER type reactors and with fast breeder reactors. The programmes solve accidents in the core, the primary circuit and the containment. A comparison is made of Czechoslovak and foreign computer programmes and their agreement proved. Also studied is the problem of radiation safety of nuclear power plants with regard to the leakage of radioactive isotopes and their detection. (J.B.)

Findings of the Work Improvement on Board (WIB) programme by the Fishery Agency in Japan.

Science.gov (United States)

Hisamune, Shuji; Kogi, Kazutaka

2015-01-01

Concerns are growing about the safety and health of seamen exposed to high risks while working on vessels. Their accident rate in 2013 was 9.9 per 1000 workers, 5 times higher than that in industry. In order to mitigate the risks of seamen, we developed the Work Improvement on Board (WIB) programme by applying participatory action-oriented training (PAOT) methods that have proven effective for reducing work-related risks in small enterprises, construction sites, and agriculture. We analysed which features of the WIB programme would be most effective for facilitating the planning and implementation of practical improvements on vessels. We examined action -oriented tools used, including a WIB action checklist and good examples, and practical improvements proposed by the participants in 1-day or half-day WIB workshops. To study the effectiveness of the WIB programme, we analysed 1121 replies of a questionnaire distributed to 1459 participants of the programme. We compared the types of improvements achieved and the improvement costs in the WIB programme with those in other PAOT programmes. The impact of the WIB programme on promoting primary prevention by seamen and fishermen was discussed. The action checklist listing practical improvements on board and good example photos apparently facilitated the planning and implementation of improvements feasible on board. The participating crews could propose readily applicable improvements of their vessels within short time. In the case of workshops held in 10 harbours between August and October 2014, participants coming from 110 vessels presented 228 improvement proposals which were mostly feasible at low cost. Among the 1121 questionnaire replies from participants of the WIB programme, over 75% evaluated the programme as necessary, practical and easy-to-understand. These positive results led to the adoption of the WIB programme for training fishermen and seamen on commercial vessels by the Fishery Agency and the Ministry of

The French nuclear programme

Energy Technology Data Exchange (ETDEWEB)

Feger, M [Ecole Nationale Superieure d' Electrotechnique de Grenoble, Institute National des Sciences et Techniques Nucleaires (Saclay), Gif-sur-Yvette, Electricite de France (France)

1990-06-01

EDF has long been interested in the use of nuclear energy for thermal power generation. After a period of apprenticeship and experiments, EDF launched a major PWR plant programme so as to reduce France's energy dependence and master generation costs. This programme, based on standardization, has achieved the desired results. It must now be adapted to suit the needs of the 21st century. For this programme, all those involved (Governmental authorities, EDF, manufacturers) were mobilized to an unprecedented extent and rigorous working methods were imposed. Experience feedback has been used to make improvements both to the installations themselves and to procedures. Results have proved satisfactory as regards nuclear safety but vigilance must be maintained. Public opinion on nuclear power is reserved we are sentenced to achieving a 'fault-free' track record, all the while mastering costs, so as to ensure the continuing use of nuclear energy. (author)

The French nuclear programme

International Nuclear Information System (INIS)

Feger, M.

1990-01-01

EDF has long been interested in the use of nuclear energy for thermal power generation. After a period of apprenticeship and experiments, EDF launched a major PWR plant programme so as to reduce France's energy dependence and master generation costs. This programme, based on standardization, has achieved the desired results. It must now be adapted to suit the needs of the 21st century. For this programme, all those involved (Governmental authorities, EDF, manufacturers) were mobilized to an unprecedented extent and rigorous working methods were imposed. Experience feedback has been used to make improvements both to the installations themselves and to procedures. Results have proved satisfactory as regards nuclear safety but vigilance must be maintained. Public opinion on nuclear power is reserved we are sentenced to achieving a 'fault-free' track record, all the while mastering costs, so as to ensure the continuing use of nuclear energy. (author)

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

Safety culture enhancement through the implementation of IAEA guidelines

International Nuclear Information System (INIS)

Mengolini, A.; Debarberis, L.

2007-01-01

This paper presents the methodology applied and the results achieved in adapting and implementing the IAEA guidelines on safety culture to a research reactor as a step towards supporting its Life Management Program. The background is presented together with the effort undertaken to develop awareness on safety culture and the enhancement programme hereafter developed. The present study shows how issues of safety culture, management awareness and commitment deserve attention and can be of fundamental relevance also for research reactors. The study presents how guidelines developed specifically for nuclear power installations (NPPs) can be adapted to meet the needs and peculiarities of other nuclear installations. Moreover, the difficulties met during the implementation of the guidelines are discussed and important information and lessons can be learnt for the nuclear industry in general

Radiation protection aspects of design for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

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

Software qualification for digital safety system in KNICS project

International Nuclear Information System (INIS)

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

2012-01-01

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

Methods and practices for verification and validation of programmable systems

International Nuclear Information System (INIS)

Heimbuerger, H.; Haapanen, P.; Pulkkinen, U.

1993-01-01

The programmable systems deviate by their properties and behaviour from the conventional non-programmable systems in such extent, that their verification and validation for safety critical applications requires new methods and practices. The safety assessment can not be based on conventional probabilistic methods due to the difficulties in the quantification of the reliability of the software and hardware. The reliability estimate of the system must be based on qualitative arguments linked to a conservative claim limit. Due to the uncertainty of the quantitative reliability estimate other means must be used to get more assurance about the system safety. Methods and practices based on research done by VTT for STUK, are discussed in the paper as well as the methods applicable in the reliability analysis of software based safety functions. The most essential concepts and models of quantitative reliability analysis are described. The application of software models in probabilistic safety analysis (PSA) is evaluated. (author). 18 refs

The MERLIN programme: Pt. 1

International Nuclear Information System (INIS)

Worswick, D.; Hindle, E.D.; Stacey, R.D.; Stevens, M.; Wickett, A.J.; GArlick, A.

1989-08-01

The MERLIN rig at the Northern Research Laboratories, Springfields, was intended to investigate the deformation behaviour of Zircaloy fuel rod cladding under conditions approximating those of a large break Loss of Coolant Accident (LOCA). In this rig, an assembly of electrically heated fuel rod simulators (6x6 cluster) was subjected to a temperature transient simulating that predicted to occur in a LOCA, including the initiation of bottom reflooding at a suitable stage. The main aim of the MERLIN programme was to investigate the extent of sub-channel blockage produced during clad deformation under conditions of high mechanical restraint, in two phase cooling conditions. The programme was to consist of four test bundles, the final two of which would be used for ballooning experiments in which high sub-channel blockage would be produced by a suitable choice of test conditions. A major part of the programme was to provide validation data for reactor accident codes used in the CEGB clad ballooning safety case for Sizewell B. This report, one of a series which describes the programme in detail, is an overview of the MERLIN programme. It provides background, summarises those reports which discuss the programme in detail and draws attention to those areas where useful information has been obtained. (author)

Unreliable alcohol testing in a shipping safety programme.

Science.gov (United States)

Helander, Anders; Hagelberg, Charlotte Asker; Beck, Olof; Petrini, Björn

2009-08-10

Within a maritime alcohol and drug testing programme, a case showing an unphysiological urine ethanol concentration (235 mmol/L, 10.8 g/L) was found. The sample contained low levels of the ethanol metabolites ethyl glucuronide (EtG) and ethyl sulphate (EtS) which confirmed prior drinking, but also tested positive for the fermenting yeast Candida albicans which suggested post-sampling ethanol formation. This and other questionable cases prompted investigation of the suitability of urine alcohol testing for the intended application. Besides the routine measurements of ethanol, illicit drugs and creatinine, randomly selected ethanol-positive and ethanol-negative urines collected within the maritime programme were checked for the presence of EtG and EtS and for fungal and bacterial growth. Data on sample handling and storage was also gathered. Ten of 15 (67%) ethanol-positive and 4 of 9 (44%) ethanol-negative urines contained yeast and/or bacteria. Among the ethanol-positive cases, 4 (27%) were obviously false positives because EtG and EtS were not detected. Microbial action as the reason for false-high ethanol concentrations was indicated in other cases. When 17 bacteria-infected but fungi-negative urines were supplemented with glucose and stored for 1 week at 21 degrees C, ethanol was formed in 2 specimens containing Escherichia coli and E. coli plus P. aeruginosa. In these samples, EtG was also formed on storage while EtS was not. The routines employed for urine collection and handling within this substance abuse programme caused many false-positive identifications of alcohol use with unintended medico-legal consequences. Unpreserved urines stored without cooling should not be used for alcohol testing, given the high risk for microbial interference.

The Programmable Logic Controller and its application in nuclear reactor systems

International Nuclear Information System (INIS)

Palomar, J.; Wyman, R.

1993-09-01

This document provides recommendations to guide reviewers in the application of Programmable Logic Controllers (PLCS) to the control, monitoring and protection of nuclear reactors. The first topics addressed are system-level design issues, specifically including safety. The document then discusses concerns about the PLC manufacturing organization and the protection system engineering organization. Supplementing this document are two appendices. Appendix A summarizes PLC characteristics. Specifically addressed are those characteristics that make the PLC more suitable for emergency shutdown systems than other electrical/electronic-based systems, as well as characteristics that improve reliability of a system. Also covered are PLC characteristics that may create an unsafe operating environment. Appendix B provides an overview of the use of programmable logic controllers in emergency shutdown systems. The intent is to familiarize the reader with the design, development, test, and maintenance phases of applying a PLC to an ESD system. Each phase is described in detail and information pertinent to the application of a PLC is pointed out

The Programmable Logic Controller and its application in nuclear reactor systems

Energy Technology Data Exchange (ETDEWEB)

Palomar, J.; Wyman, R. [Lawrence Livermore National Lab., CA (United States)

1993-09-01

This document provides recommendations to guide reviewers in the application of Programmable Logic Controllers (PLCS) to the control, monitoring and protection of nuclear reactors. The first topics addressed are system-level design issues, specifically including safety. The document then discusses concerns about the PLC manufacturing organization and the protection system engineering organization. Supplementing this document are two appendices. Appendix A summarizes PLC characteristics. Specifically addressed are those characteristics that make the PLC more suitable for emergency shutdown systems than other electrical/electronic-based systems, as well as characteristics that improve reliability of a system. Also covered are PLC characteristics that may create an unsafe operating environment. Appendix B provides an overview of the use of programmable logic controllers in emergency shutdown systems. The intent is to familiarize the reader with the design, development, test, and maintenance phases of applying a PLC to an ESD system. Each phase is described in detail and information pertinent to the application of a PLC is pointed out.

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

International Nuclear Information System (INIS)

2009-09-01

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

Multinational design evaluation programme - 2009 annual report

International Nuclear Information System (INIS)

2010-06-01

The Multinational Design Evaluation Programme (MDEP) was established in 2006 as a multinational initiative to develop innovative approaches to leverage the resources and knowledge of the national regulatory authorities who are currently or will be tasked with the review of new reactor power plant designs. MDEP comprises 13 countries' nuclear regulatory authorities and is structured under 3 design-specific working groups and 3 issue-specific working groups which meet several times a year. The OECD/NEA facilitates MDEP's activities by acting as technical secretariat for the programme. The MDEP Policy Group (PG) and the Steering Technical Committee (STC) oversee the programme. MDEP's main objectives can be defined as follows: - to enhance multilateral co-operation within existing regulatory frameworks; - to encourage multinational convergence of codes, standards and safety goals; - to implement the MDEP products in order to facilitate the licensing of new reactors, including those being developed by the Generation IV International Forum. To carry out the work, two main lines of activity have been implemented: - the exploration of opportunities for harmonisation of regulatory practices; - the cooperation on the safety reviews of specific reactor designs. MDEP engages with key stakeholders involved in ensuring the safety of new reactor designs, manufacturing, construction and operation. At this time, these stakeholders include other national regulatory authorities and international organisations involved in ensuring nuclear safety including the IAEA, Western European Nuclear Regulators' Association (WENRA), NEA Committees on Nuclear Regulatory Activities (CNRA) and Safety of Nuclear Installations (CSNI), the various reactor vendors, nuclear component manufacturers, mechanical and electrical standards development organisations, reactor operators and licensees and key industry representatives such as World Nuclear Association (WNA). To this end, the MDEP has organised a

Nuclear Safety Review for the Year 2009

International Nuclear Information System (INIS)

2010-07-01

The global nuclear community is experiencing a period of dynamic change. The introduction of new nuclear power plants, the rapid expansion of existing nuclear power programmes and the wider use of radioactive sources and ionizing radiation in general highlight the need for continued and improved international cooperation to address the associated challenges. The increasingly multinational nature of today's nuclear business and activities underscores this need. In this context, it is particularly important to note that the establishment of adequate safety infrastructure and capacity cannot be left to fall behind. The safety performance of the nuclear industry has remained at a high level. Various safety performance indicators, such as those related to unplanned reactor shutdowns, safety equipment availability, radiation exposures to workers, radioactive waste management and radioactive releases to the environment have shown steady improvement over the past two decades, with some levelling off in recent years. Nevertheless, it is necessary to avoid complacency and to continuously improve and strengthen the existing global nuclear safety and security regime so that nuclear technologies can be introduced or their use expanded in a safe and secure manner to meet the world's needs for human well-being and socio-economic development. The Agency continues to support and promote increased participation in the global nuclear safety and security regime as a framework for achieving high levels of safety in nuclear activities worldwide. Through consideration of the global trends, issues and challenges observed in 2009, four key themes in global nuclear safety were identified: 1) continuing international cooperation and emerging coordination for new and expanding nuclear power programmes; 2) improving the long term management of radioactive and nuclear materials; 3) capacity building for sustainable nuclear safety; and 4) strengthening global and regional networking activities

Enhancing operational nuclear safety

International Nuclear Information System (INIS)

Sengoku, Katsuhisa

2008-01-01

Since Chernobyl, the dictum A n accident anywhere is an accident everywhere i s a globally shared perception. The paper presents challenges to the international nuclear community: globalization, sustainable and dynamic development, secure, safe and clean energy supply, nuclear r enaissance , public concern for nuclear safety, nuclear security, and technology and management. Strong national safety infrastructures and international cooperation are required to maintain a high level of nuclear safety and security worldwide. There is an increasing number of countries thinking of going nuclear: Morocco, Indonesia, Iran, Poland, Turkey, Bangladesh, Egypt, Vietnam, Chile, Nigeria, Malaysia, Thailand, Uruguay, Tunisia, Algeria. Another serious incident will jeopardize the prospect of nuclear renaissance. Safety and security are preconditions for countries newly introducing NPP as well as for those with mature nuclear programmes. The Global Nuclear Safety Regime (GNSR) is referred to as the institutional, legal and technical framework to achieve worldwide implementation of the safety of nuclear installations. At the top of the framework is the Convention on Nuclear Safety which covers the nuclear power plants. The convention has 56 contracting parties which meet triennially where national reports are presented and subject to the review of peers. The International Atomic Energy Agency (IAEA) undertakes a programme to foster the GNSR through the establishment of IAEA safety standards and related publications. The programme provides for the application of standards for the (1) safety of nuclear installations, (2) safety of radioactive sources, (3) safe transport of radioactive material and (4) management of radioactive waste. It also provides for the security of nuclear installations, nuclear material and radioactive material. The safety standards hierarchy is as follows: safety fundamental, safety requirements and safety guides. The safety fundamentals are the bases for IAEA

Life Cycle V and V Process for Hardware Description Language Programs of Programmable Logic Device-based Instrumentation and Control Systems

International Nuclear Information System (INIS)

Cha, K. H.; Lee, D. Y.

2010-01-01

Programmable Logic Device (PLD), especially Complex PLD (CPLD) or Field Programmable Logic Array (FPGA), has been growing in interest in nuclear Instrumentation and Control (I and C) applications. PLD has been applied to replace an obsolete analog device or old-fashioned microprocessor, or to develop digital controller, subsystem or overall system on hardware aspects. This is the main reason why the PLD-based I and C design provides higher flexibility than the analog-based one, and the PLD-based I and C systems shows better real-time performance than the processor-based I and C systems. Due to the development of the PLD-based I and C systems, their nuclear qualification has been issued in the nuclear industry. Verification and Validation (V and V) is one of necessary qualification activities when a Hardware Description Language (HDL) is used to implement functions of the PLD-based I and C systems. The life cycle V and V process, described in this paper, has been defined as satisfying the nuclear V and V requirements, and it has been applied to verify Correctness, Completeness, and Consistency (3C) among design outputs in a safety-grade programmable logic controller and a safety-critical data communication system. Especially, software engineering techniques such as the Fagan Inspection, formal verification, simulated verification and automated testing have been defined for the life cycle V and V tasks of behavioral, structural, and physical design in VHDL

Developing Infrastructure for New Nuclear Power Programmes

International Nuclear Information System (INIS)

2011-09-01

Many countries are interested in introducing or expanding nuclear energy programmes because they regard nuclear power as a clean and stable source of electricity that can help to mitigate the impact of climate change. However, the March 2011 accident at the Fukushima Daiichi nuclear power plant in Japan - caused by an earthquake and tsunami of unprecedented proportions - demonstrated that there is a constant need to improve global nuclear safety, despite the great progress made in the previous 25 years. A 'safety first' approach needs to become fully entrenched among nuclear power plant operators, governments and regulators everywhere. Safety first must also be the watchword for Member States considering the introduction of nuclear power. I believe that all IAEA Member States should have access to nuclear power if they wish to add it their energy mix. While it is up to each country to decide whether or not to opt for nuclear power, the IAEA has a key role to play in ensuring that the development of nuclear power programmes takes place in a safe, efficient, responsible and sustainable manner. The IAEA has developed guidelines and milestones to help countries work in a systematic way towards the introduction of nuclear power. Use of the 'Milestones' approach can increase transparency both within a country introducing nuclear power, and between it and other States. This brochure summarizes the services which the IAEA offers to Member States considering introducing nuclear power. These include advice on proper planning, building the required human resources and infrastructure, establishing legal and regulatory frameworks, and ensuring the highest standards of safety and security, without increasing proliferation risks. The IAEA offers independent know-how on the construction, commissioning, startup and operation of nuclear reactors. Through the Technical Cooperation programme, we provide targeted support to 'newcomer' countries in response to national development needs

US nuclear safety. Review and experience

International Nuclear Information System (INIS)

Hanauer, S.H.

1977-01-01

The paper deals with the evolution of reactor safety principles, design bases, regulatory requirements, and experience in the United States. Safety concerns have evolved over the years, from reactivity transients and shut-down systems, to blowdowns and containment, to severe design basis accidents and mitigating systems, to the performance of actual materials, systems and humans. The primary safety concerns of one epoch have been superseded in considerable measure by those of later times. Successive plateaus of technical understanding are achieved by solutions being found to earlier problems. Design studies, research, operating experience and regulatory imperatives all contribute to the increased understanding and thus to the safety improvements adopted and accepted. The improvement of safety with time, and the ability of existing reactors to operate safely in the face of new concerns, has confirmed the correctness and usefulness of the defence-in-depth approach and safety margins used in safety design in the United States of America. A regulatory programme such as the one in the United States justifies its great cost by its important contributions to safety. Yet only the designers, constructors and operators of nuclear power plants can actually achieve public safety. The regulatory programme audits, assesses and spot-checks the actual work. Since neither materials nor human beings are flawless, mistakes will be made; that is why defence-in-depth and safety margins are provided. The regulatory programme should enhance safety by decreasing the frequency of uncorrected mistakes. Maintenance of public safety also requires technical and managerial competence and attention in the organizations responsible for nuclear plants as well as regulatory organizations. (author)

Motivational factors influencing small construction and auto repair enterprises to participate in occupational health and safety programmes

DEFF Research Database (Denmark)

Kvorning, Laura Veng; Hasle, Peter; Christensen, Ulla

2015-01-01

the processmeaningful. Contextual factors, as experienced by the owner-managers, influenced the motivation foractive participation. These included inter alia general attitude towards authorities and procedures, accessto relevant projects and technical equipment, the characteristics of the manager, and the workplace......Small enterprises have limited resources to prioritise occupational health and safety (OHS) so regulatorsand other stakeholders have developed programmes to support them. The present study analysed thefactors influencing active participation of small construction and auto repair enterprises...... foractive participation also depended on the content of the prevention package, the economic support andthe possibility for facilitation. The decision to start the implementation process depended on whether theowner-managers acknowledged the need for the new OHS approach and whether they found...

Nuclear Safety Review for the Year 2008

International Nuclear Information System (INIS)

2009-07-01

Nuclear technologies are increasingly seen as important solutions for meeting a number of challenges. Enabling the peaceful use of nuclear technology to support global energy demands and other human needs must be accompanied by deliberate, internationally-coordinated actions to minimize the potential for nuclear accidents and terrorism. While in recent years, the safety performance of the nuclear industry has been good, it is important to avoid any complacency. The Agency continues to support and promote the global nuclear safety and security regime as a framework for worldwide achievement of high levels of safety and security in nuclear activities. In 2008, three general themes can be observed from the global trends, issues and challenges in nuclear safety: the continuous improvements in strengthening safety worldwide through international cooperation; an expected increase of new entrant nuclear power programmes and the expansion of existing programmes; and safety and security synergy. Regarding continuous improvements to strengthen safety worldwide, the focus was on operating experience feedback and knowledge networking; and self-assessment and peer review. In the areas of new entrant nuclear programmes and expansion of existing nuclear programmes, activities centred on national safety infrastructures; human resources and capacity building; regulatory independence; nuclear incident and emergency preparedness and response; spent fuel and radioactive waste management; and multinational aspects of nuclear activities. In the area of safety and security synergy, in 2008 there was increasing awareness that processes need to be in place to ensure that safety activities do not compromise security and vice versa. As outlined in Safety Fundamentals No. SF-1, the prime responsibility for safety must rest with the person or organization responsible for facilities and activities that give rise to radiation risks. An effective legal and governmental framework for safety

ICRP publication 26. Its applicability in a nuclear power programme

International Nuclear Information System (INIS)

Wilson, R.; Donnelly, K.

1980-01-01

Ontario Hydro is a major Canadian provincial utility with more than 5 GW(e) installed nuclear electricity generating capacity and with a planned commitment to an additional 8.5 GW(e), all units being of the CANDU pressurized heavy-water type. The radiation protection programme, in addition to complying with Canadian Federal regulations, has been consistent with the philosophy and intent of ICRP recommendations and is frequently reviewed to ensure compliance with these recommendations, the most recent of which is ICRP-26. The application of the ALARA principle in this power reactor programme is described. A set of general guidelines has been established, the main features of which are: (a) achieving a dose consumption per unit of electricity generated which is low compared with reactors of a similar type; (b) ensuring that stations are operable with the dose equivalent of their labour-dictated manpower; (c) ensuring that the risk to atomic radiation workers is compatible with a corporate fatality rate standard of 8 man-hours worked. Achievement of these guidelines has necessitated implementing a continued dose-management programme. This programme is described generally. The cost applied to justify a dose reduction of 1 man.Sv is given, and a comparison is made with the equivalent life costs this implies and the costs used by safety agencies for other risk-reduction activities. Finally, some practical problems associated with some of the recommendations of ICRP-26 are discussed. (author)

Sensitivity and uncertainty analyses applied to criticality safety validation. Volume 2

International Nuclear Information System (INIS)

Broadhead, B.L.; Hopper, C.M.; Parks, C.V.

1999-01-01

This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies developed in Volume 1 to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the existing S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently in use by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The methods for application of S/U and generalized linear-least-square methodology (GLLSM) tools to the criticality safety validation procedures were described in Volume 1 of this report. Volume 2 of this report presents the application of these procedures to the validation of criticality safety analyses supporting uranium operations where enrichments are greater than 5 wt %. Specifically, the traditional k eff trending analyses are compared with newly developed k eff trending procedures, utilizing the D and c k coefficients described in Volume 1. These newly developed procedures are applied to a family of postulated systems involving U(11)O 2 fuel, with H/X values ranging from 0--1,000. These analyses produced a series of guidance and recommendations for the general usage of these various techniques. Recommendations for future work are also detailed

Natural safety indicators and their application to repository safety cases

International Nuclear Information System (INIS)

Miller, B.

2002-01-01

Radiological dose and risk are the standard end-points calculated in all performance assessments. Their calculation requires, however, assumptions to be made for future human behaviour. To complement dose and risk, other safety indicators have been suggested which do not require such assumptions to be made. One proposed set of safety indicators are the concentrations and fluxes of naturally-occurring chemical species in the environment which may be compared with the performance assessment predictions of repository releases. Such comparisons can be valid because both the natural and repository species would occur in the same system and their transport behaviour would be controlled by exactly the same processes at the same rates. Although simple in concept, there is currently no consensus on the most appropriate comparisons to make or on the interpretation of such comparisons. A number of national and international research projects are evaluating this proposed approach, including an IAEA Co-ordinated Research Programme. These projects suggest that that the approach appears to be workable and that it may be a valuable component of a safety case, complementing the dose and risk presentations. Further work is, however, necessary to develop the approach to a level where it may be confidently applied in further performance assessments in a consistent and methodical manner. (author)

Risk-based safety indicators

International Nuclear Information System (INIS)

Szikszai, T.

1997-01-01

The presentation discusses the following issues: The objectives of the risk-based indicator programme. The characteristics of the risk-based indicators. The objectives of risk-based safety indicators - in monitoring safety; in PSA applications. What indicators? How to produce the risk based indicators? PSA requirements

Radiation protection aspects in the design of nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

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

Publicly administrated nuclear waste management research programme 1994-1996. Final report

Energy Technology Data Exchange (ETDEWEB)

Vuori, S. [ed.] [VTT Energy, Espoo (Finland)

1997-09-01

The main objective of the JYT-programme has been to provide the authorities with independent information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into following main topic areas: (1) bedrock structure and stability, rock investigation methods and characteristics and flow of ground water, (2) release of radionuclides from a repository and subsequent transport in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management, (4) natural analogue studies, (5) waste management technology and costs and (6) socio political and other societal issues and environmental impact assessment.

Publicly administrated nuclear waste management research programme 1994-1996. Final report

International Nuclear Information System (INIS)

Vuori, S.

1997-09-01

The main objective of the JYT-programme has been to provide the authorities with independent information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into following main topic areas: (1) bedrock structure and stability, rock investigation methods and characteristics and flow of ground water, (2) release of radionuclides from a repository and subsequent transport in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management, (4) natural analogue studies, (5) waste management technology and costs and (6) socio political and other societal issues and environmental impact assessment

Leveraging Safety Programs to Improve and Support Security Programs

Energy Technology Data Exchange (ETDEWEB)

Leach, Janice [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Snell, Mark K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Pratt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sandoval, S. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-10-01

There has been a long history of considering Safety, Security, and Safeguards (3S) as three functions of nuclear security design and operations that need to be properly and collectively integrated with operations. This paper specifically considers how safety programmes can be extended directly to benefit security as part of an integrated facility management programme. The discussion will draw on experiences implementing such a programme at Sandia National Laboratories’ Annular Research Reactor Facility. While the paper focuses on nuclear facilities, similar ideas could be used to support security programmes at other types of high-consequence facilities and transportation activities.

State Supervision of Mines. Strategy and Programme for 2007-2011

International Nuclear Information System (INIS)

2007-01-01

State Supervision of Mines (SodM) supervises the observance of legal regulations that apply to the search for, extraction of and storage of minerals. The SodM focuses on aspects of safety, health, environment, efficient extraction and soil movements. Every five years, the SodM draws up a strategic document. This strategic document is a sequel to the report 'Strategic policy 2002 to 2007'. This report provides a short overview of the realizations of the last five years. Moreover an analysis is included of the policy developments in the fields of mineral extraction, safety, health and environment. Subsequently the consequences of these developments for SodM are examined. Based on these developments an elaboration is provided of the initiatives taken by SodM and an outlook of the programme of supervision projects for the next five years. This document also includes a communication plan, which illustrates when and how SodM goes public. [mk] [nl

A safety assessment methodology applied to CNS/ATM-based air traffic control system

Energy Technology Data Exchange (ETDEWEB)

Vismari, Lucio Flavio, E-mail: lucio.vismari@usp.b [Safety Analysis Group (GAS), School of Engineering at University of Sao Paulo (Poli-USP), Av. Prof. Luciano Gualberto, Trav.3, n.158, Predio da Engenharia de Eletricidade, Sala C2-32, CEP 05508-900, Sao Paulo (Brazil); Batista Camargo Junior, Joao, E-mail: joaocamargo@usp.b [Safety Analysis Group (GAS), School of Engineering at University of Sao Paulo (Poli-USP), Av. Prof. Luciano Gualberto, Trav.3, n.158, Predio da Engenharia de Eletricidade, Sala C2-32, CEP 05508-900, Sao Paulo (Brazil)

2011-07-15

In the last decades, the air traffic system has been changing to adapt itself to new social demands, mainly the safe growth of worldwide traffic capacity. Those changes are ruled by the Communication, Navigation, Surveillance/Air Traffic Management (CNS/ATM) paradigm , based on digital communication technologies (mainly satellites) as a way of improving communication, surveillance, navigation and air traffic management services. However, CNS/ATM poses new challenges and needs, mainly related to the safety assessment process. In face of these new challenges, and considering the main characteristics of the CNS/ATM, a methodology is proposed at this work by combining 'absolute' and 'relative' safety assessment methods adopted by the International Civil Aviation Organization (ICAO) in ICAO Doc.9689 , using Fluid Stochastic Petri Nets (FSPN) as the modeling formalism, and compares the safety metrics estimated from the simulation of both the proposed (in analysis) and the legacy system models. To demonstrate its usefulness, the proposed methodology was applied to the 'Automatic Dependent Surveillance-Broadcasting' (ADS-B) based air traffic control system. As conclusions, the proposed methodology assured to assess CNS/ATM system safety properties, in which FSPN formalism provides important modeling capabilities, and discrete event simulation allowing the estimation of the desired safety metric.

A safety assessment methodology applied to CNS/ATM-based air traffic control system

International Nuclear Information System (INIS)

Vismari, Lucio Flavio; Batista Camargo Junior, Joao

2011-01-01

In the last decades, the air traffic system has been changing to adapt itself to new social demands, mainly the safe growth of worldwide traffic capacity. Those changes are ruled by the Communication, Navigation, Surveillance/Air Traffic Management (CNS/ATM) paradigm , based on digital communication technologies (mainly satellites) as a way of improving communication, surveillance, navigation and air traffic management services. However, CNS/ATM poses new challenges and needs, mainly related to the safety assessment process. In face of these new challenges, and considering the main characteristics of the CNS/ATM, a methodology is proposed at this work by combining 'absolute' and 'relative' safety assessment methods adopted by the International Civil Aviation Organization (ICAO) in ICAO Doc.9689 , using Fluid Stochastic Petri Nets (FSPN) as the modeling formalism, and compares the safety metrics estimated from the simulation of both the proposed (in analysis) and the legacy system models. To demonstrate its usefulness, the proposed methodology was applied to the 'Automatic Dependent Surveillance-Broadcasting' (ADS-B) based air traffic control system. As conclusions, the proposed methodology assured to assess CNS/ATM system safety properties, in which FSPN formalism provides important modeling capabilities, and discrete event simulation allowing the estimation of the desired safety metric.

Biotechnology 2000: a new German R&D programme

OpenAIRE

Ekkehard Warmuth

1991-01-01