Publications
List of titles sorted by date
Avis techniques du CSIN n° 14
(2012)
Déterminer la pertinence des structures organisationnelles, des ressources et des compétences des exploitants nucléaires
Avis techniques du CSIN - Nos 7-8
(2005)
EPS vivante et son utilisation dans le processus décisionnel en matière de sûreté nucléaire - Mise au point et utilisation de l'EPS temps réel dans les centrales nucléaires
Detailed publication list
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Nuclear Power Plant Operating Experience 2015-2017
English
, 74 pages, published: 04/21/20
NEA#7482
Available online at:
http://www.oecd-nea.orgwww.oecd-nea.org/jcms/pl_53449/nuclear-power-plant-operating-experience-from-the-iaea/nea-incident-reporting-system-2015-2017
The International Reporting System for Operating Experience (IRS) is an essential system for the international exchange of information on safety related events at nuclear power plants worldwide. The fundamental objective of the IRS is to enhance the safety of nuclear power plants through the sharing of timely and detailed information on such events, and the lessons that can be learnt from them, to reduce the chance of recurrence at other plants. The first edition of this publication covered safety related events reported between 1996 and 1999. This seventh edition covers the 2015-2017 period and highlights important lessons learnt from a review of the 246 event reports received from participating states during those years. The IRS is jointly operated and managed by the OECD Nuclear Energy Agency (OECD/NEA) and the International Atomic Energy Agency (IAEA).
CSNI Technical Opinion Paper No. 17
Fire Probabilistic Safety Assessments
for Nuclear Power Plants: 2019 Update
English
, published: 05/27/19
NEA#7417
Available online at:
http://www.oecd-nea.org/nsd/pubs/2019/7417-csni-top17.pdf
CSNI Technical Opinion Paper No. 17: Fire Probabilistic Safety Assessments for Nuclear
Power Plants: 2019 Update provides an authoritative review of the current status and
use of the fire PSA in nuclear power plants. The report demonstrates that while fires
at a particular plant site are highly dependent on plant and site specific factors, they
are nonetheless an important contributor to overall risk. Insights from fire PSAs are
generally found to be aligned with operating experience and to be representative of
the expected plant response, making them valuable in addressing risk. This report
should be useful for regulators overseeing the use of fire PSAs in nuclear installations,
practitioners in understanding the considerations for performing or reviewing fire PSAs,
and researchers in identifying areas requiring further study.
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Phenomena Identification and Ranking Table
R&D Priorities for Loss-of-Cooling and Loss-of-Coolant Accidents in Spent Nuclear Fuel Pools
English
, published: 08/03/18
NEA#7443
Available online at:
http://www.oecd-nea.org/nsd/pubs/2018/7443-pheno_id_rank_table.pdf
The present report is a follow up to this status report, documenting the results of a Phenomena Identification and Ranking Table (PIRT) exercise conducted by the NEA. This PIRT exercise identified SFP accident phenomena that are of high importance and yet are highly uncertain, thus highlighting their primary interest for further studies. The report recommends further support for existing experimental programmes and the establishment of a number of new programmes to focus, for example, on large-scale thermal-hydraulic experiments on the coolability of partly or completely uncovered spent-fuel assemblies and the investigation of spray cooling for uncovered spent-fuel assemblies in typical storage racks.
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Five Years after the Fukushima Daiichi Accident
Nuclear Safety Improvements and Lessons Learnt
English
, 76 pages, published: 02/29/16
NEA#7284
Available online at:
http://www.oecd-nea.org/nsd/pubs/2016/7284-five-years-fukushima.pdf
Other language(s):
- English:
Five Years after the Fukushima Daiichi Accident (Executive summary)
- Japanese:
福島第一原子力発電所事故後の５年：原子力安全の改善と教訓
Countries around the world continue to implement safety improvements and corrective actions based on lessons learnt from the 11 March 2011 accident at the Fukushima Daiichi nuclear power plant. This report provides a high-level summary and update on these activities, and outlines further lessons learnt and challenges identified for future consideration. It focuses on actions taken by NEA committees and NEA member countries, and as such is complementary to reports produced by other international organisations.
It is in a spirit of openness and transparency that NEA member countries share this information to illustrate that appropriate actions are being taken to maintain and enhance the level of safety at their nuclear facilities. Nuclear power plants are safer today because of these actions. High priority follow-on items identified by NEA committees are provided to assist countries in continuously benchmarking and improving their nuclear safety practices.
The Safety Culture of an Effective Nuclear Regulatory Body
English
, 32 pages, published: 02/04/16
NEA#7247
Available online at:
http://www.oecd-nea.org/nsd/pubs/2016/7247-scrb2016.pdf
The fundamental objective of all nuclear safety regulatory bodies is to ensure that activities related to the peaceful use of nuclear energy are carried out in a safe manner within their respective countries. In order to effectively achieve this objective, the nuclear regulatory body requires specific characteristics, one of which is a healthy safety culture.
This regulatory guidance report describes five principles that support the safety culture of an effective nuclear regulatory body. These principles concern leadership for safety, individual responsibility and accountability, co-operation and open communication, a holistic approach, and continuous improvement, learning and self-assessment.
The report also addresses some of the challenges to a regulatory body's safety culture that must be recognised, understood and overcome. It provides a unique resource to countries with existing, mature regulators and can be used for benchmarking as well as for training and developing staff. It will also be useful for new entrant countries in the process of developing and maintaining an effective nuclear safety regulator.
Implementation of Defence in Depth at Nuclear Power Plants
Lessons Learnt from the Fukushima Daiichi Accident
English
, 45 pages, published: 01/28/16
NEA#7248
Available online at:
http://www.oecd-nea.org/nsd/pubs/2016/7248-did-npp.pdf
Defence in depth (DiD) is a concept that has been used for many years alongside tools to optimise nuclear safety in reactor design, assessment and regulation. The 2011 Fukushima Daiichi nuclear power plant accident provided unique insight into nuclear safety issues and raised questions about the tools used at nuclear power plants, including the effectiveness of the DiD concept, and whether DiD can be enhanced and its implementation improved.
This regulatory guidance booklet examines and provides advice on the implementation of DiD. A key observation is that the use of the DiD concept remains valid after the Fukushima Daiichi accident. Indeed, lessons learnt from the accident, and the accident?s impact on the use of DiD, have reinforced the fundamental importance of DiD in ensuring adequate safety.
This report is intended primarily for nuclear regulatory bodies, although information included herein is expected to be of interest to licensees, nuclear industry organisations and the general public.
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The Characteristics of an Effective Nuclear Regulator
NEA/CNRA/R(2014)1
English
, 32 pages, published: 07/04/14
NEA#7185
Available online at:
http://www.oecd-nea.org/nsd/pubs/2014/7185-regulator.pdf
Both national and international organisations agree that the fundamental objective of all nuclear safety regulatory bodies -- the regulator's prime purpose -- is to ensure that nuclear licensees operate their facilities at all times in a safe manner. Much has been written about ways to improve regulatory processes or to improve the effectiveness of a regulatory body, including in previous OECD/NEA regulatory guidance booklets. But until now, none have focused on the characteristics of an effective nuclear safety regulator.
Effective organisations are those that have good leadership and are able to transform strategic direction into operational programmes. Effectiveness is about how well the organisation is achieving its fundamental purpose -- in the case of a nuclear safety regulator, ensuring that licensees operate their facilities and discharge their obligations in a safe manner.
This regulatory guidance booklet describes the characteristics of an effective nuclear safety regulator in terms of roles and responsibilities, principles and attributes. Each of the characteristics discussed in this report is a necessary feature of an effective nuclear safety regulator but no one characteristic is sufficient on its own. It is the combination of these characteristics that leads to the effectiveness of a nuclear regulatory body. The report provides a unique resource to countries with existing, mature regulators and can be used for benchmarking as well as training and developing staff. It will also be useful for new entrant countries in the process of developing and maintaining an effective nuclear safety regulator.
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The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt
English
, 68 pages, published: 09/10/13
NEA#7161
Volume of the series:
Nuclear Safety
Available online at:
http://www.oecd-nea.org/pub/2013/7161-fukushima2013.pdf
Other language(s):
- Japanese:
福島第一原子力発電所事故
OECD/NEA原子力安全の対応と教訓
This report outlines the response of the OECD Nuclear Energy Agency (NEA) and its member countries to the March 2011 accident at TEPCO's Fukushima Daiichi nuclear power plant. All NEA members took early action to ensure and confirm the continued safety of their nuclear power plants and the protection of the public. Consistent with its objective of maintaining and further developing the scientific, technological and legal bases for safe nuclear energy, the NEA has assisted its member countries in their individual and collective responses to the accident. It has also provided direct assistance to the relevant authorities in Japan. These actions are summarised in the report along with lessons learnt thus far. Key messages are offered as a means to help strengthen the basis for nuclear safety and its implementation in all countries using nuclear power.
CSNI Technical Opinion Papers No. 16
Defence in Depth of Electrical Systems
English
, 48 pages, published: 05/17/13
NEA#7070
Available online at:
http://www.oecd-nea.org/nsd/docs/2013/7070-top-16.pdf
As all safety systems in the majority of existing nuclear power plants use the preferred power supply, any voltage surges in these systems could lead to common-cause failures. In the event of an unusual electrical system transient, it is essential that safety-related equipment be isolated or protected from the fault in order to ensure its ability to safely shut down the reactor and remove decay heat.
Based on the analysis of the voltage surges observed at Forsmark-1 in 2006 and Olkiluoto-1 in 2008, this technical opinion paper summarises the current state of knowledge of in-plant and external grid-related challenges to nuclear power plant safety-related electrical equipment. It will be of particular interest to nuclear safety regulators, nuclear power plant operators and grid system regulators and operators.
Crisis Communication: Facing the Challenges - Proceedings
Workshop Proceedings, Madrid, Spain, 9-10 May 2012
English
, 240 pages, published: 05/06/13
NEA#7067
Available online at:
http://www.oecd-nea.org/nsd/docs/2013/7067-crisis-communication.pdf
As manifested by an increasingly globalised media, a nuclear accident anywhere quickly becomes a potential concern for people everywhere. It is therefore of prime importance that nuclear regulators’ communication strategies take into consideration the expectations and concerns of the public and provide sound information not only for the people of the affected country, but also for citizens worldwide. Public trust is a key element in being able to do so effectively and of particular importance when there are consequences for people or the environment. International co-operation can play a fundamental role in helping to improve crisis communication on national and global scales in the event of a nuclear accident or radiological emergency. These proceedings contain the papers, recommendations and conclusions of the workshop, which was attended by over 180 experts from 27 countries and 6 international organisations.
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Nuclear Power Plant Operating Experience
from the IAEA/NEA International Reporting System for Operating Experience:
2009-2011
English
, 60 pages, published: 12/31/12
NEA#7120
, ISBN: 978-92-64-99193-4
Available online at:
http://www.oecd-nea.org/nsd/docs/2012/7120-iaea-nea-irs-2009-2011.pdf
The application of lessons learnt from the International Reporting System for Operating Experience (IRS) is an essential element for enhancing the safe operation of nuclear power plants (NPPs) throughout the world. The IRS provides a mechanism for the exchange of information related to the incident, actions taken, root cause analysis and lessons learnt. This feedback on how to adequately remedy, or avoid, possible challenges and precursors is of paramount importance to operational safety. The IRS improves international awareness of potential challenges, actual incidents and “precursors” in NPP operations. The heightened awareness generated by feedback from operating experience has resulted in numerous improvements to equipment, procedures and training in many NPPs. The application of operational feedback also benefits the design of the next generation of NPPs. Operating experience has demonstrated that design modification issues documented in IRS reports can have a significant impact on safety. The IRS is jointly operated and managed by the OECD Nuclear Energy Agency (OECD/NEA) and the International Atomic Energy Agency (IAEA).
Avis techniques du CSIN n° 15
Gestion du vieillissement des installations du cycle du combustible nucléaire
Français
, 44 pages, published: 12/31/12
NEA#6991
, ISBN: 978-92-64-99182-8
Available online at:
http://www.oecd-nea.org/nsd/docs/2012/6991-top-15-fr.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers No. 15
- Chinese:
核设施安全委员会技术见解报告 No.15 - 核燃料循环设施老化管理
La gestion du vieillissement des installations du cycle du combustible consiste, comme pour toute autre installation nucléaire, à garantir la disponibilité des fonctions de sûreté sur toute leur durée de vie tout en tenant compte des modifications intervenues avec le temps et l’usage. Cet avis technique identifie et compare les stratégies et les bonnes pratiques utilisées pour faire face au vieillissement physique et à l’obsolescence des installations, depuis leur conception jusqu’à leur démantèlement. Il devrait intéresser les autorités de sûreté nucléaire, les exploitants d’installations du cycle du combustible ainsi que les chercheurs qui travaillent sur ce sujet.
CSNI Technical Opinion Papers No. 15
Ageing Management of Nuclear Fuel Cycle Facilities
English
, 40 pages, published: 12/31/12
NEA#6990
, ISBN: 978-92-64-99181-1
Available online at:
http://www.oecd-nea.org/nsd/docs/2012/6990-top-15.pdf
Other language(s):
- Français:
Avis techniques du CSIN n° 15
- Chinese:
核设施安全委员会技术见解报告 No.15 - 核燃料循环设施老化管理
Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into account the changes that occur with time and use. This technical opinion paper identifies a set of good practices by benchmarking strategies and good practices on coping with physical ageing and obsolescence from the facility design stage until decommissioning. It should be of particular interest to nuclear safety regulators, fuel cycle facilities operators and fuel cycle researchers.
Challenges in Long-term Operation of Nuclear Power Plants
Implications for Regulatory Bodies
English
, 32 pages, published: 09/21/12
NEA#7074
, ISBN: 978-92-64-99187-3
Available online at:
http://www.oecd-nea.org/nsd/docs/2012/cnra-r2012-5.pdf
Other language(s):
- Français:
Défis de l'exploitation à long terme des centrales nucléaires
Nuclear power reactors have become a major source of electricity supply in many countries and, based on the experience of safe and reliable operation, many operators have sought and received authorisation for long-term operation beyond the period assumed in the plant’s design. Acceptance of a nuclear power plant for long-term operation must be based on evidence that the plant will operate safely over the extended period of service. This requires an assessment of the current and projected condition of the plant and, in particular, of the systems that perform fundamental safety functions, to ensure that these systems will continue to perform their safety functions during the extended operating period. Programmes for long-term operation must be informed by operating experience and must also consider and assess environmental impacts.
This guidance document is intended to assist regulatory organisations in assessing and approving the long-term operation safety assessments submitted by operators. It outlines the fundamental principles that should govern decisions on authorisation for long-term operation. It also describes regulatory challenges and considerations that may arise in an assessment of a plant for long-term operation.
Défis de l'exploitation à long terme des centrales nucléaires
Implications pour les autorités de sûreté
Français
, 32 pages, published: 09/21/12
NEA#7075
, ISBN: 978-92-64-99188-0
Available online at:
http://www.oecd-nea.org/nsd/docs/2012/cnra-r2012-5-fr.pdf
Other language(s):
- English:
Challenges in Long-term Operation of Nuclear Power Plants
Les réacteurs nucléaires sont devenus une source majeure de production d'électricité dans de nombreux pays et, sur la base d'une exploitation sûre et fiable, de nombreux exploitants ont demandé et obtenu une autorisation d'exploitation à long terme au-delà de la durée prévue à la conception. L’acceptation de l'exploitation à long terme d’une centrale doit être basée sur la preuve que la sûreté sera maintenue pendant la période de prolongement de sa durée de vie. Il est nécessaire d'évaluer l'état actuel et prévu de la centrale et, en particulier, des systèmes qui assurent les fonctions fondamentales de sûreté, afin de garantir que ces systèmes vont continuer à réaliser ces fonctions pendant la période d’exploitation supplémentaire. Les programmes d’exploitation à long terme doivent utiliser et évaluer le retour d'expérience d’exploitation et prendre également en compte les impacts sur l’environnement.
Ce guide vise à aider les autorités de sûreté dans l’analyse et l’approbation des évaluations de sûreté soumises par les exploitants pour l’exploitation à long terme. Il expose les principes fondamentaux sur lesquels doivent être basées les décisions d’autorisation d’exploitation à long terme. Il décrit également les défis et les considérations qui peuvent survenir dans l’évaluation d’une centrale pour l’exploitation à long terme.
Nuclear Fuel Safety Criteria Technical Review
Second Edition
English
, 80 pages, published: 09/14/12
NEA#7072
, ISBN: 978-92-64-99178-1
Available online at:
http://www.oecd-nea.org/nsd/reports/2012/nea7072-fuel-safety-criteria.pdf
Most of the current nuclear fuel safety criteria were established during the 1960s and early 1970s. Although these criteria were validated against experiments with fuel designs available at that time, a number of tests were based on unirradiated fuels. Additional verification was performed as these designs evolved, but mostly with the aim of showing that the new designs adequately complied with existing criteria, and not to establish new limits.
In 1996, the OECD Nuclear Energy Agency (NEA) reviewed existing fuel safety criteria, focusing on new fuel and core designs, new cladding materials and industry manufacturing processes. The results were published in the Nuclear Fuel Safety Criteria Technical Review of 2001. The NEA has since re-examined the criteria. A brief description of each criterion and its rationale are presented in this second edition, which will be of interest to both regulators and industry (fuel vendors, utilities).
OECD Nuclear Energy Agency (NEA) follow-up to the TEPCO Fukushima Daiichi nuclear accident
Extracts from NEA News
English
, 16 pages, published: 06/27/12
NEA#6888
Available online at:
http://www.oecd-nea.org/pub/nea6888-follow-up-fukushima.pdf
The NEA has undertaken a number of activities following the March 2011 accident at the Fukushima Daiichi nuclear power plant in Japan. This brochure contains three extracts from NEA News published in the months following the accident: Fukushima (what happened, consequence, follow-up), published June 2011; Fukushima: liability and compensation, published December 2011; and The NEA integrated response to the Fukushima Daiichi nuclear accident, published June 2012. Together these extracts allow the reader to understand better the causes, consequences and importance of the NEA’s response to the Fukushima Daiichi accident (2012).
CSNI Technical Opinion Papers No. 14
Nuclear Licensee Organisational Structures, Resources and Competencies: Determining Their Suitability
English
, 16 pages, published: 05/15/12
NEA#6912
, ISBN: 978-92-64-99175-0
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/csni-r2011-13.pdf
Other language(s):
- Français:
Avis techniques du CSIN n° 14
The way in which nuclear licensees’ organisations are structured and resourced clearly has a potential impact on nuclear safety. As experience has continually demonstrated, operating organisations with a strong training programme for personnel, adequate resourcing and overall effective leadership and management perform more effectively in times of crisis than those lacking in one or more of these areas. In parallel, the nuclear industry is developing new resource deployment strategies which are making increased use of contractors and leading to changes in organisational structure, which in turn create challenges for the continued safe operation of nuclear facilities. This technical opinion paper represents the consensus among human and organisational factor specialists in NEA member and associated countries on the methods, approaches and good practices to be followed in designing an organisation with a strong safety focus while meeting business needs. It also considers some of the attributes that an organisation which is effectively managing its resources and capabilities might demonstrate.
Avis techniques du CSIN n° 14
Déterminer la pertinence des structures organisationnelles, des ressources et des compétences des exploitants nucléaires
Français
, 20 pages, published: 05/15/12
NEA#6913
, ISBN: 978-92-64-99176-7
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/csni-r2011-13-fr.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers No. 14
La structure organisationnelle des exploitants ainsi que leurs ressources ont clairement un impact sur la sûreté nucléaire. L’expérience continue à montrer que les organisations qui bénéficient d’un programme de formation du personnel solide, de ressources adéquates et de services de direction et de gestion efficaces fonctionnent mieux en temps de crise que celles qui présentent des lacunes dans un ou plusieurs de ces domaines. En parallèle, le secteur nucléaire développe de nouvelles stratégies de déploiement des ressources qui font appel à un nombre croissant de fournisseurs et font l’objet de modifications structurelles, qui à leur tour créent des défis pour une exploitation sûre dans la durée des installations nucléaires. Cet avis technique présente le consensus de spécialistes des facteurs humains et organisationnels des pays membres de l’AEN et des pays associés sur les méthodes, approches et bonnes pratiques à suivre dans le cadre de la conception d’une organisation qui tient fortement compte de la sûreté mais aussi des impératifs commerciaux. Il aborde également les caractéristiques d’une organisation qui gère efficacement ses ressources et ses capacités.
Main Benefits from 30 Years of Joint Projects in Nuclear Safety
English
, 132 pages, published: 05/04/12
NEA#7073
, ISBN: 978-92-64-99171-2
Available online at:
http://www.oecd-nea.org/nsd/reports/2012/nea7073-30-years-joint-safety-projects.pdf
One of the major achievements of the OECD Nuclear Energy Agency (NEA) is the knowledge it has helped to generate through the organisation of joint international research projects. Such projects, primarily in the areas of nuclear safety and radioactive waste management, enable interested countries, on a cost-sharing basis, to pursue research or the sharing of data with respect to particular areas or issues. Over the years, more than 30 joint projects have been conducted with wide participation of member countries.
The purpose of this report is to describe the achievements of the OECD/NEA joint projects on nuclear safety research that have been carried out over the past three decades, with a particular focus on thermal-hydraulics, fuel behaviour and severe accidents. It shows that the resolution of specific safety issues in these areas has greatly benefited from the joint projects’ activities and results. It also highlights the added value of international co-operation for maintaining unique experimental infrastructure, preserving skills and generating new knowledge.
Computational Fluid Dynamics (CFD) for Nuclear Reactor Safety Applications
Workshop Proceedings, CFD4NRS-3, Bethesda, Maryland, USA, 14-16 September 2010
English
, published: 03/22/12
NEA#7076
Available online at:
http://www.oecd-nea.org/nsd/csni/cfd/workshops/CFD4NRS-3/
Computational fluid dynamics (CFD) is increasingly being adopted in nuclear reactor safety (NRS) analyses as a tool which enables a better description of specific safety-relevant phenomena occurring in nuclear reactors. The OECD Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) has in recent years conducted important activities in the CFD area, including the organisation of three workshops. The CFD4NRS-3 workshop was the third in the series and was held in Bethesda, Maryland, USA on 14-16 September 2010. A total of 200 experts participated. These proceedings contain the 4 keynote lectures, including the synthesis of results for the Tee-junction Benchmark, and the 57 technical papers presented at the workshop.
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Le rôle de l'autorité de sûreté nucléaire dans l'évaluation de la surveillance par l'exploitant des services sous-traités
Français
, 40 pages, published: 12/19/11
NEA#6827
, ISBN: 978-92-64-99167-5
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/cnra-r2011-4-f.pdf
Other language(s):
- English:
The Nuclear Regulator's Role in Assessing Licensee Oversight of Vendor and Other Contracted Services
Les services sous-traités font partie intégrante de la conception, de la construction et de l’exploitation d’une installation nucléaire. Les évolutions du secteur de l’industrie nucléaire, notamment une disponibilité de l’expertise nucléaire en mutation, un marché international de l’approvisionnement en expansion et l’introduction de nouvelles technologies, incitent les exploitants à recourir de plus en plus à ces services. Tous ces changements ont placé les exploitants et les autorités de sûreté face à des défis en termes de maintien de l’expertise nucléaire, de gestion efficace des interfaces entre les exploitants et les entreprises extérieures, et de surveillance de la qualité de fabrication de ces dernières dans le contexte d’une plus grande diversité multinationale. L’autorité de sûreté doit relever ces défis pour garantir que les exploitants continuent à assumer leur responsabilité en matière de sûreté des installations, quel que soit le fournisseur des biens et services ou le lieu où se déroulent les activités impliquées dans la chaîne d’approvisionnement. Ce rapport vise à aider les autorités de sûreté à évaluer leurs pratiques actuelles en matière de contrôle réglementaire du recours des exploitants à des entreprises extérieures, et à les adapter le cas échéant en fonction de l’évolution de la situation.
CSNI Technical Opinion Papers – No. 13
LOCA Criteria Basis and Test Methodology
English
, 40 pages, published: 09/21/11
NEA#6986
, ISBN: 978-92-64-99154-5
Volume of the series:
Nuclear Safety
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/csni-r2011-7.pdf
Other language(s):
- Français:
Avis techniques du CSIN – n° 13
Acceptance criteria for emergency core cooling systems (ECCS) define the maximum temperature and degree of oxidation in order to avoid excessive embrittlement and hence failure of the fuel cladding, which would affect core cooling in the case of a loss-of-coolant accident (LOCA). The criteria are mainly based on experimental data obtained in the 1970s-80s. Several types of tests have been performed to evaluate structural integrity and embrittlement of the cladding under LOCA conditions, and consequently different test methodologies have been used for determining the cladding embrittlement criteria. The current trend towards high burn-up and the use of new cladding alloys has increased the need for international discussions on these test methodologies and acceptance criteria. In response, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Fuel Safety produced this technical opinion paper, which should be of particular interest to nuclear safety regulators, nuclear power plant operators and fuel researchers.
Avis techniques du CSIN – n° 13
Méthodologies d'essai et bases de calcul des critères APRP
Français
, 48 pages, published: 09/21/11
NEA#6987
, ISBN: 978-92-64-99161-3
Volume of the series:
Sûreté nucléaire
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/csni-r2011-7f.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers – No. 13
Les critères d’acceptation du circuit de refroidissement de secours du cœur définissent la température et le niveau d’oxydation à ne pas dépasser pour éviter la fragilisation excessive, et donc la rupture, des gaines de combustible, qui pourrait affecter le refroidissement du cœur dans le cas d’un accident de perte de réfrigérant primaire (APRP). Ces critères ont été établis principalement à partir de données expérimentales obtenues dans les années 1970 et 80. Plusieurs types d’essais ont été réalisés pour évaluer l’intégrité structurale et la fragilisation des gaines dans les conditions d'un APRP, et diverses méthodologies utilisées pour déterminer les seuils de fragilisation des gainages. Avec l'emploi de plus en plus fréquent de combustibles à haut taux de combustion et de nouveaux alliages pour les gainages, il a été jugé utile d’engager une réflexion au niveau international sur les méthodologies d’essai et les critères d'acceptation. Ainsi, le Comité de l’AEN sur la sûreté des installations nucléaires (CSIN) et son Groupe de travail sur la sûreté du combustible ont rédigé cet avis technique qui devrait intéresser tout particulièrement les autorités de sûreté, les exploitants de centrales nucléaires ainsi que les chercheurs travaillant sur le combustible nucléaire.
Improving Nuclear Regulation
NEA Regulatory Guidance Booklets, Volumes 1-14
English
, 270 pages, published: 05/30/11
NEA#6905
, ISBN: 978-92-64-99162-0
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/cnra-r2011-10.pdf
A common theme throughout the series of NEA regulatory guidance reports, or “green booklets”, is the premise that the fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are continuously maintained and operated in an acceptably safe manner. In meeting this objective the regulator must bear in mind that it is the operator that has responsibility for safely operating the nuclear facility; the role of the regulator is to assess and to provide assurance regarding the operator’s activities in terms of assuming that responsibility.
The full series of these reports was brought together in one edition for the first time in 2009 and was widely found to be a useful resource. This second edition comprises 14 volumes, including the latest on The Nuclear Regulator's Role in Assessing Licensee Oversight of Vendor and Other Contracted Services. The reports address various challenges that could apply throughout the lifetime of a nuclear facility, including design, siting, manufacturing, construction, commissioning, operation, maintenance and decommissioning. The compilation is intended to serve as a knowledge management tool both for current regulators and the new nuclear professionals and organisations entering the regulatory field.
Experimental Facilities for Sodium Fast Reactor Safety Studies
Task Group on Advanced Reactor Experimental Facilities (TAREF)
English
, 144 pages, published: 04/15/11
NEA#6908
, ISBN: 978-92-64-99155-2
Volume of the series:
Nuclear Safety
Available online at:
http://www.oecd-nea.org/nsd/docs/2010/csni-r2010-12.pdf
This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for sodium fast reactors and identifies priorities for organising international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems.
The Nuclear Regulator's Role in Assessing Licensee Oversight of Vendor and Other Contracted Services
English
, 38 pages, published: 03/31/11
NEA#6910
, ISBN: 978-92-64-99157-6
Volume of the series:
Nuclear Safety
Available online at:
http://www.oecd-nea.org/nsd/docs/2011/cnra-r2011-4.pdf
Other language(s):
- Français:
Le rôle de l'autorité de sûreté nucléaire dans l'évaluation de la surveillance par l'exploitant des services sous-traités
Contracted services are an integral part of the design, construction and operation of a nuclear facility. Changes in the nuclear industry sector, including varied availability of nuclear expertise, the expansion of the international supply market and the introduction of new technologies, have tended to increase licensees’ use of contracted services. These changes have created challenges for licensees and regulators related to the retention of nuclear expertise, the effective management of the interfaces between the licensees and contractors, and the oversight of contractor manufacturing quality in the context of greater multinational diversity. The regulatory body must address these challenges to provide assurance that the licensees maintain their responsibility for the safety of the facilities, regardless of who provides goods and services or where the activities involved in the supply chain take place. This report is intended to assist regulatory bodies in assessing their current practices for the regulatory oversight of licensees’ use of contractors, and adapting them where necessary to meet the evolving situation.
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Nuclear Fuel Behaviour under Reactivity-initiated Accident (RIA) Conditions
State-of-the-art Report
English
, 208 pages, published: 03/24/10
NEA#6847
, ISBN: 978-92-64-99113-2
Available online at:
http://www.oecd-nea.org/nsd/reports/2010/nea6847-behaviour-RIA.pdf
Considerable experimental and analytical work has been performed in recent years which has led to a broader and deeper understanding of phenomena related to reactivity-initiated accidents (RIAs). Further, newly designed fuels – such as mixed-oxide (MOX) fuel and rods with new cladding – have been introduced which might behave differently than those used previously, both under normal operating conditions and during transients. Compared with 20 years ago, fuel burn-up has been significantly increased. These and other factors have led the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Fuel Safety to produce this state-of-the-art report. The report should be of particular interest to nuclear safety regulators, nuclear plant operators and fuel researchers.
Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS)
Workshop Proceedings, Grenoble, France, 10-12 September 2008
English
, published: 03/19/10
NEA#6879
Available online at:
http://www.oecd-nea.org/nsd/csni/cfd/workshops/XCFD4NRS/index.html
Computational fluid dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety (NRS) analyses as a tool that enables a better description of specific safety-relevant phenomena occurring in nuclear reactors. The NEA Committee on the Safety of Nuclear Installations (CSNI) has in recent years conducted important activities in the CFD area, including the organisation of two workshops. The “XCFD4NRS” workshop was the second in the series and was held in Grenoble, France in September 2008. A total of 147 experts from 22 countries took part. These proceedings contain the five keynote lectures, summaries of the activities of three CFD writing groups and the 59 technical papers presented at the workshop.
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Experimental Facilities for Gas-cooled Reactor Safety Studies
Task Group on Advanced Reactor Experimental Facilities (TAREF)
English
, 88 pages, published: 12/31/09
NEA#6864
, ISBN: 978-92-64-99110-1
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/nea6864-TAREF.pdf
This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organising international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems.
CSNI Technical Opinion Papers - No. 12
Research on Human Factors in New Nuclear Plant Technology
English
, 40 pages, published: 12/11/09
NEA#6844
, ISBN: 978-92-64-99116-3
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/nea6844-TOP12-Eng.pdf
Other language(s):
- Français:
Avis techniques du CSIN - n° 12
It is a dynamic time for the nuclear power sector. Existing reactor control rooms are undergoing various forms of modernisation. New reactors are being built in many countries and advanced reactors are being designed through international co-operation to support power generation for decades to come. The new technologies and concepts that are being considered in this context could impact upon the roles of the plant operators and thus plant safety. It is therefore important that the potential implications – both positive and negative – are evaluated and understood.
Through this technical opinion paper, the NEA Committee on the Safety of Nuclear Installations (CSNI) has sought to identify a set of research topics that should be explored in order to enhance knowledge of the human and organisational factors concerned. Research to address the topics described in this paper will provide the technical basis to help ensure that the benefits of new technology are realised and that the potential negative effects are minimised.
This paper should be of particular interest to research organisations and other stakeholders (including regulatory agencies, international organisations and industry organisations) that could support this research and benefit from its results.
Avis techniques du CSIN - n° 12
Recherches sur le facteur humain dans les nouvelles centrales nucléaires
Français
, 44 pages, published: 12/11/09
NEA#6845
, ISBN: 978-92-64-99117-0
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/nea6845-TOP12-Fr.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 12
Le secteur nucléaire connaît actuellement une phase dynamique. La modernisation des salles de commande des centrales prend diverses formes. De nouveaux réacteurs sont construits dans de nombreux pays. Des modèles avancés sont conçus dans le cadre de la coopération internationale afin d’assurer la production d'électricité au cours des prochaines décennies. Les nouveaux concepts et technologies étudiés dans ce contexte peuvent avoir un impact sur le rôle des exploitants de centrales et par conséquence sur la sûreté. Il est donc important d'évaluer et de comprendre ces incidences potentielles, qu'elles soient positives ou négatives.
Dans cet avis technique, le Comité de l’AEN sur la sûreté des installations nucléaires (CSIN) a cherché à identifier un ensemble de sujets de recherche à étudier pour la connaissance des facteurs humains et organisationnels concernés. Les recherches menées sur les sujets décrits devront fournir les connaissances techniques qui permettront de tirer parti des nouvelles technologies et d'en réduire le plus possible les éventuels effets négatifs.
Cet avis présentera un intérêt particulier pour les établissements de recherche et les autres acteurs (autorités de sûreté, organisations internationales et entreprises industrielles) susceptibles de contribuer à ces recherches et d'en bénéficier.
Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions
State-of-the-art Report
English
, 376 pages, published: 06/29/09
NEA#6846
, ISBN: 978-92-64-99091-3
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/nea6846_LOCA.pdf
Considerable experimental and analytical work has been performed in recent years which has led to a broader and deeper understanding of phenomena related to loss-of-coolant accidents (LOCAs). Further, new cladding alloys have been produced, which might behave differently than the previously used Zircaloy-4, both under normal operating conditions and during transients. Compared with 20 years ago, fuel burn-up has been significantly increased. These and other factors have led the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Fuel Safety to produce this state-of-the-art report. The report should be of particular interest to nuclear safety regulators, nuclear power plant operators and nuclear fuel researchers.
Improving Nuclear Regulation
Compilation of NEA Regulatory Guidance Booklets
English
, 208 pages, published: 04/02/09
NEA#6275
, ISBN: 978-92-64-99075-3
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/nea6275_Improving_Nuclear_Regulation.pdf
A common theme throughout the series of NEA regulatory guidance reports, or “green booklets”, is the premise that the fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are operated at all times and later decommissioned in an acceptably safe manner. In meeting this objective the regulator must keep in mind that it is the operator that has responsibility for safely operating a nuclear facility; the role of the regulator is to oversee the operator’s activities as related to assuming that responsibility.
For the first time, the full series of these reports have been brought together in one edition. As such, it is intended to serve as a knowledge management tool both for current regulators and the younger generation of nuclear experts entering the regulatory field. While the audience for this publication is primarily nuclear regulators, the information and ideas may also be of interest to nuclear operators, other nuclear industry organisations and the general public.
Avis techniques du CSIN - No. 11
Améliorer la maintenance des centrales nucléaires en optimisant les performances humaines et organisationnelles
Français
, 32 pages, published: 02/26/09
NEA#6154
, ISBN: 978-92-64-99071-5
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/NEA6154_TOP_11_FR.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 11
Les erreurs durant la maintenance et les essais périodiques contribuent de manière significative aux incidents dans les centrales. Ces erreurs peuvent ne pas toujours être mises en évidence par les essais post-maintenance et peuvent longtemps passer inaperçues jusqu’à ce que le système touché soit amené à fonctionner. Il importe donc que le processus de maintenance des centrales prenne en considération l’impact possible des erreurs humaines et organisationnelles et qu’il comporte des mesures adaptées pour réduire au minimum ces erreurs.
Le Comité sur la sûreté des installations nucléaires (CSIN) de l’AEN et son Groupe de travail sur les facteurs humains et organisationnels ont organisé un atelier international pour analyser l’impact des facteurs humains et organisationnels sur la maintenance. Cet avis technique reflète le consensus des spécialistes des facteurs humains et organisationnels des pays membres de l’AEN sur des pratiques et approches conseillées pour réaliser les opérations de maintenance dans les centrales nucléaires. Il présente un système pour intégrer la prise en compte systématique des facteurs humains et organisationnels dans le processus de maintenance d’une centrale. Cet avis devrait particulièrement intéresser les autorités de sûreté nucléaire et les exploitants des centrales nucléaires.
CSNI Technical Opinion Papers - No. 11
Better Nuclear Plant Maintenance: Improving Human and Organisational Performance
English
, 28 pages, published: 02/26/09
NEA#6153
, ISBN: 978-92-64-99065-4
Available online at:
http://www.oecd-nea.org/nsd/reports/2009/NEA6153_TOP_11_ENG.pdf
Other language(s):
- Français:
Avis techniques du CSIN - No. 11
Errors during maintenance and periodic testing are significant contributors to plant events. These errors may not always be revealed by post-maintenance tests and may remain undetected for extended periods until the affected system is called upon to function. It is therefore important that the plant maintenance process take into account the potential impact of human and organisational errors, and that it incorporate suitable measures to minimise the potential for such errors.
The NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Human and Organisational Factors organised an international workshop to discuss the role of human and organisational performance on maintenance. This technical opinion paper represents the consensus of specialists on human and organisational factors in NEA member countries on commendable practices and approaches to dealing with nuclear power plant maintenance. It sets out a framework for including a systematic consideration of human and organisational factors in the plant maintenance process. The paper should be of particular interest to nuclear safety regulators and nuclear power plant operators.
CSNI Technical Opinion Papers - No. 10
The Role of Human and Organisational Factors in Nuclear Power Plant Modifications
English
, 28 pages, published: 02/03/09
NEA#6315
, ISBN: 978-92-64-99064-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea6315_TOP_10_ENG.pdf
Other language(s):
- Français:
Avis techniques du CSIN - n° 10
Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; feedback from operating experience; and opportunities for improved plant safety, reliability or capability. However, experience has also shown that weaknesses in the design and/or implementation of modifications can present significant challenges to plant safety. They can also have a considerable impact on the commercial performance of the plant. It is therefore important that the plant modification process reflect a recognition of the potential impact of human errors and that it incorporate suitable measures to minimise the potential for such errors.
In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Human and Organisational Factors organised an international workshop in 2003 to discuss the role of human and organisational performance in the nuclear plant modification process. This technical opinion paper represents the consensus of specialists in human and organisational factors (HOF) in the NEA member countries on commendable practices and approaches to dealing with nuclear plant modifications. It considers factors that should be taken into account when developing a modification process and identifies some lessons learnt from application of the process. The paper should be of particular interest of nuclear safety regulators and nuclear power plant operators.
Avis techniques du CSIN - n° 10
Le rôle des facteurs humains et organisationnels dans les modifications des centrales nucléaires
Français
, 28 pages, published: 02/03/09
NEA#6316
, ISBN: 978-92-64-99069-2
Available online at:
http://www.oecd-nea.org/nsd/reports/nea6316_TOP_10_FR.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 10
Il peut être nécessaire d’apporter des modifications à une centrale nucléaire pour diverses raisons : le vieillissement des systèmes, des structures et des composants de la centrale, l’obsolescence du matériel et des logiciels, le retour d’expérience et les possibilités d’améliorer la sûreté, la fiabilité ou les capacités de la centrale. Or, l’expérience a montré que des défaillances au niveau de la conception et/ou de la mise en œuvre des modifications pouvaient présenter des défis importants pour la sûreté des centrales. Elles peuvent également avoir une incidence non négligeable sur les résultats commerciaux de l’installation. C’est pourquoi, il importe que le processus de modification concrétise la prise en compte de l’impact possible des erreurs humaines et qu’il comporte des dispositions appropriées pour réduire au maximum l’éventualité de ces erreurs.
Dans ce contexte, le Comité sur la sûreté des installations nucléaires (CSIN) et son Groupe de travail sur les facteurs humains et organisationnels ont organisé, en 2003, un atelier international pour examiner le rôle des performances humaines et organisationnelles dans le processus de modification des centrales nucléaires. Cet avis technique reflète le consensus des spécialistes des facteurs humains et organisationnels des pays membres de l’AEN sur les pratiques et approches recommandées en matière de modification des centrales nucléaires. Il examine les facteurs qui devraient être pris en compte au cours de l’élaboration d’un processus de modification et recense quelques-uns des enseignements tirés de l’application de ce processus. Cet avis technique devrait particulièrement intéresser les exploitants des centrales nucléaires ainsi que les autorités de sûreté nucléaire.
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Assurer la sûreté nucléaire : la mission des autorités réglementaires
Français
, 60 pages, published: 06/13/08
NEA#6274
, ISBN: 978-92-64-99051-7
Available online at:
http://www.oecd-nea.org/nsd/reports/2008/nea6274-autorites.pdf
Other language(s):
- English:
The Regulatory Goal of Assuring Nuclear Safety
La mission fondamentale de toutes les autorités de sûreté nucléaire consiste à s’assurer que les installations nucléaires sont à tout moment exploitées de manière sûre puis démantelées en toute sécurité. Dans l’accomplissement de sa mission, l’autorité de sûreté ne doit pas oublier que la responsabilité d’exploiter en toute sécurité une installation nucléaire revient à l’exploitant et que la sienne est de contrôler les activités de l’exploitant pour s’assurer que les conditions de fonctionnement de l’installation sont sûres.
Aujourd’hui l’autorité de sûreté dispose de nombreuses sources d’informations sur la sûreté d’une installation nucléaire : les rapports d’inspection, le retour d’expérience, les résultats des recherches, les examens périodiques de sûreté, les résultats des études probabilistes de sûreté (EPS), les enseignements tirés des audits de l’AIEA, pour n’en citer que quelques-unes. Un des principaux défis consiste alors à recueillir et à analyser systématiquement ces informations pour se faire une idée globale du niveau de sûreté de l’installation en question puis ensuite de juger si ce niveau est acceptable. C’est pour aider ses pays membres à relever ce défi que le Comité sur les activités nucléaires réglementaires (CANR) de l’Agence de l’OCDE pour l’énergie nucléaire a préparé ce rapport.
Le rapport s’intéresse essentiellement à la façon dont l’autorité de sûreté peut systématiquement recueillir et analyser de manière intégrée toutes les informations pertinentes sur la sûreté pour porter un jugement valide sur l’acceptabilité du niveau de la sûreté des installations qu’elle contrôle. Ce rapport s’adresse donc avant tout aux autorités de sûreté nucléaire, même si les informations et idées qu’il renferme sont susceptibles d’intéresser des exploitants nucléaires, d’autres organisations dans l’industrie nucléaire ainsi que certains membres du public.
CSNI Collective Statement on Support Facilities for Existing and Advanced Reactors/Déclaration collective du CSIN sur les installations de recherche pour les réacteurs actuels et avancés
The Function of OECD/NEA Joint Projects - NEA Committee on the Safety of Nuclear Installations (CSNI)/Utilité des projets communs de l'OCDE/AEN - Comité de l'AEN sur la sûreté des installations nucléaires (CSIN)
Bilingual
, 16 pages, published: 05/28/08
NEA#6379
, ISBN: 978-92-64-99052-4
Available online at:
http://www.oecd-nea.org/nsd/docs/2008/csni-r2008-5.pdf
The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide.
Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritise technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors.
This statement constitutes a reference for future CSNI activities and for safety authorities, R&D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area.
Le Comité de l’AEN sur la sûreté des installations nucléaires (CSIN) a récemment achevé une étude sur la disponibilité et l’utilisation des installations en soutien aux études de sûreté pour les réacteurs nucléaires actuels et avancés. L’étude révèle qu’au cours des dernières années des mesures importantes ont été prises afin de soutenir les installations expérimentales pour la sûreté, essentiellement consistant en la mise en œuvre de projets multinationaux centrés sur le caractère unique de certaines installations dans le monde.
Au vu de l’expérience positive des projets de recherche en sûreté, il a été recommandé que des efforts soient faits pour hiérarchiser les questions techniques associées aux conceptions de réacteurs avancés (Génération IV) et de proposer des solutions pour obtenir efficacement les données nécessaires au moyen d’une recherche internationale coordonnée en préparant une extension progressive de la recherche en sûreté au-delà des besoins correspondant aux réacteurs actuellement en exploitation.
Cette déclaration constitue une référence pour les activités futures du CSIN ainsi que pour les autorités de sûreté, les centres de R-D et l’industrie en vue d’initiatives coordonnées de recherche internationale dans le domaine de la sûreté nucléaire.
The Role of Research in a Regulatory Context (RRRC-2)
Workshop Proceedings, Paris, France, 5 December 2007
English
, 136 pages, published: 02/29/08
NEA#6377
, ISBN: 978-92-64-99045-6
Available online at:
http://www.oecd-nea.org/nsd/docs/2008/csni-r2008-3.pdf
This workshop enabled the exchange of experience among regulators, research managers and industry on the needs, priorities and foreseeable trends for nuclear safety research in a regulatory context. It also addressed the means that are or can be used for effectively performing such research.
The presentations highlighted priority safety issues, at present and in the near term, for operating plants and new reactors. During the workshop, participants discussed the challenges that the nuclear community will face in the long term for performing safety evaluations of advanced reactor designs, and explored various avenues for organising the research and infrastructure that will be needed.
These proceedings will be of particular interest to nuclear specialists and research managers wishing to obtain an international perspective of current and foreseeable needs in regulatory-driven nuclear safety research.
The Regulatory Goal of Assuring Nuclear Safety
English
, 56 pages, published: 02/29/08
NEA#6273
, ISBN: 978-92-64-99044-9
Available online at:
http://www.oecd-nea.org/nsd/reports/2008/nea6273-goal.pdf
Other language(s):
- Français:
Assurer la sûreté nucléaire : la mission des autorités réglementaires
The fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are operated, as well as decommissioned, in an acceptably safe manner. However, in meeting this objective the regulator must keep in mind that it is the operator that has responsibility for safely operating a nuclear facility; the role of the regulator is to oversee the operator’s activities as related to assuming that responsibility.
There are currently many sources of information available to the regulator pertaining to safety at any given nuclear facility, such as inspection reports, operating experience reports, research results, periodic safety reviews, probabilistic safety analysis (PSA) results, insights from IAEA reviews and other similar information. A major challenge for the regulator is to systematically collect and analyse this information in order to arrive at an integrated assessment of the level of safety of the particular facility and then to make a judgement about its acceptability. In order to assist member countries in addressing this challenging question, the Committee on Nuclear Regulatory Activities (CNRA) of the OECD Nuclear Energy Agency (NEA) has sponsored this report.
The primary focus of the report is on how the regulatory body can systematically collect and make an integrated analysis of all the relevant safety information available to it and arrive at a sound judgement on the acceptability of the level of safety of the facilities that it regulates. It therefore follows that the target audience for this report is primarily nuclear regulators, although the information and ideas may also be of interest to nuclear operators, other nuclear industry organisations and segments of civil society.
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Transparency of Nuclear Regulatory Activities
Workshop Proceedings,Tokyo and Tokai-Mura, Japan, 22-24 May 2007
English
, 316 pages, published: 11/16/07
NEA#6256
, ISBN: 978-92-64-04095-3
Available online at:
http://www.oecd-nea.org/nsd/pubs/2007/6256-transparency-nra.pdf
One of the main missions of nuclear regulators is to protect the public, and this cannot be completely achieved without public confidence. The more a regulatory process is transparent, the more such confidence will grow. Despite important cultural differences across countries, a number of common features characterise media and public expectations regarding any activity with an associated risk.
A common understanding of transparency and main stakeholders' expectations in the field of nuclear safety were identified during this workshop, together with a number of conditions and practices aimed at improving the transparency of nuclear regulatory activities. These conditions and practices are described herein, and will be of particular interest to all those working in the nuclear regulatory field. Their implementation may, however, differ from one country to another depending on national context.
CSNI Technical Opinion Papers - No. 9
Level-2 PSA for Nuclear Power Plants
English
, 32 pages, published: 04/20/07
NEA#5352
, ISBN: 978-92-64-99008-1
Available online at:
http://www.oecd-nea.org/nsd/reports/2007/nea5352-level2-psa.pdf
Other language(s):
- Français:
Avis techniques du CSIN - N° 9
This technical opinion paper represents the consensus of risk analysts in NEA member countries on the current state of the art of level-2 probabilistic safety assessment (PSA) and its applications in accident management of nuclear power plants. Level-2 PSA models the phenomena that could occur following the onset of core damage that have the potential to challenge the containment integrity and lead to a release of radioactive material to the environment. The paper's objective is to present decision makers in the nuclear field with a clear technical opinion on the status as implemented in industrial PSAs.
The intended audience is primarily nuclear safety regulators, researchers and industry representatives dealing with safety management and severe accidents. Government authorities and nuclear power plant operators may also be interested in the paper.
CSNI: NEA Committee on the Safety of Nuclear Installations.
Avis techniques du CSIN - N° 9
EPS de niveau 2 des centrales nucléaires
Français
, 34 pages, published: 04/20/07
NEA#5353
, ISBN: 978-92-64-99009-8
Available online at:
http://www.oecd-nea.org/nsd/reports/2007/nea5353-eps2.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 9
Cet avis technique représente le consensus des analystes de risque dans les pays membres de l’AEN sur l'état de l’art en matière d’études probabilistes de sûreté (EPS) et leurs applications à la gestion des accidents dans les centrales nucléaires. Les EPS de niveau 2 modélisent les phénomènes susceptibles de survenir après l'amorce d'une détérioration du cœur, de compromettre l’intégrité du confinement et d'entraîner le rejet de matières radioactives dans l’environnement. L’objectif de ce document est d'offrir aux décideurs dans ce domaine un avis technique clair sur l'état de l'EPS telle qu'elle est utilisée dans l'industrie.
Cet avis s'adresse principalement aux autorités de sûreté nucléaire, aux chercheurs et aux industriels concernés par la gestion de la sûreté et les accidents graves, mais il pourrait également intéresser les autorités publiques et les exploitants de centrales nucléaires.
CSIN : Comité de l'AEN sur la sûreté des installations nucléaires.
Nuclear Safety Research in OECD Countries
Support Facilities for Existing and Advanced Reactors (SFEAR)
English
, 108 pages, published: 03/28/07
NEA#6158
, ISBN: 978-92-64-99005-0
Available online at:
http://www.oecd-nea.org/nsd/docs/2007/csni-r2007-6.pdf
This report provides an overview of experimental facilities that can be used to address nuclear safety research issues in OECD member countries, and identifies priorities for organising international co-operative programmes centred on selected facilities. The information has been gathered and analysed by a Senior Group of Experts on Nuclear Safety Research, in the context of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) aimed at maintaining critical experimental infrastructure for nuclear safety studies in member countries.
Evaluation of Uncertainties in Relation to Severe Accident and Level-2 Probabilistic Safety Analysis - CD-ROM
Workshop Proceedings, Aix-en-Provence, France, 7-9 November 2005
English
, 65 pages, published: 03/13/07
NEA#6053
Available online at:
http://www.oecd-nea.org/nsd/reports/2007/nea6053-uncertainties.html
Uncertainty in relation to several severe accident phenomena plays a major role in probabilistic safety analyses involving beyond-design-basis accident scenarios for nuclear power plants. The technical papers presented herein will be valuable for nuclear safety analysts, nuclear power plant designers and R&D managers, especially with regard to unresolved severe accident issues or issues where risk uncertainty is high.
Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS) - CD-ROM
Workshop Proceedings, Garching (Munich), Germany, 5-7 September 2006
English
, 65 pages, published: 03/13/07
NEA#6298
Available online at:
http://www.oecd-nea.org/nsd/reports/2007/nea6298-benchmarking.html
On 5-7 September 2006, the OECD Nuclear Energy Agency organised a workshop on Benchmarking of CFD Codes for Application to Nuclear Reactor Safety (CFD4NRS) in co-operation with the International Atomic Energy Agency. The workshop was hosted in Germany by the Gesellschaft für Anlagen und Reaktorsicherheit (GRS). The purpose of the workshop was to provide a forum for numerical analysts and experimentalists to exchange information on nuclear reactor safety activities relevant to computational fluid dynamics (CFD) validation, with the objective of providing input to create a practical, state-of-the-art, web-based assessment matrix on the use of CFD for nuclear reactor safety applications. These proceedings contain the 39 technical papers presented at the workshop, which was attended by 100 participants.
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Learning from Nuclear Regulatory Self-assessment
International Peer Review of the CSN Report on Lessons Learnt from the Essential Service Water System Degradation Event at the Vandellos Nuclear Power Plant
English
, 52 pages, published: 10/10/06
NEA#6161
, ISBN: 92-64-02310-0
Available online at:
http://www.oecd-nea.org/nsd/reports/2006/nea6161-vandellos.pdf
Nuclear regulatory self-assessment together with the benchmarking of regulatory practices against those of other countries operating nuclear power plants are key elements in maintaining a high level of nuclear safety. In that light, the Spanish Consejo de Seguridad Nuclear (CSN) formally asked the OECD Nuclear Energy Agency (NEA) to establish an international peer review team to assess the CSN report on the lessons learnt as a result of the 2004 Vandellós II event involving essential service water system degradation.
The International Review Team considers the CSN report prepared in follow-up to the Vandellós event to be a commendable effort in regulatory self-assessment. The report, complemented by this international peer review, should enable the CSN to take appropriate action to ensure that its regulatory supervision is in line with best international practice.
Nuclear Power Plant Operating Experiences from the IAEA/NEA Incident Reporting System
2002-2005
English
, 56 pages, published: 05/17/06
NEA#6150
, ISBN: 92-64-02294-5
Available online at:
http://www.oecd-nea.org/nsd/reports/2006/nea6150-irs.pdf
The Incident Reporting System (IRS) is an essential element of the international operating experience feedback system for nuclear power plants. The IRS is jointly operated and managed by the Nuclear Energy Agency (NEA), a semi-autonomous body within the Organisation for Economic Co-operation and Development (OECD), and the International Atomic Energy Agency (IAEA), a specialised agency within the United Nations System.
Building, Measuring and Improving Public Confidence in the Nuclear Regulator
Workshop Proceedings, Ottawa, Canada, 18-20 May 2004
English
, 236 pages, published: 05/16/06
NEA#5999
, ISBN: 92-64-02590-1
Available online at:
http://www.oecd-nea.org/nsd/pubs/2006/5999-building-measuring.pdf
An important factor for public confidence in the nuclear regulator is the general public trust of the government and its representatives, which is clearly not the same in all countries. Likewise, cultural differences between countries can be considerable, and similar means of communication between government authorities and the public may not be universally effective.
Nevertheless, this workshop identified a number of common principles for the communication of nuclear regulatory decisions that can be recommended to all regulators. They have been cited in particular for their ability to help build, measure and/or improve overall public confidence in the nuclear regulator.
L'utilisation du retour d'expérience : défis pour les autorités de sûreté nucléaire
Français
, 32 pages, published: 04/12/06
NEA#6137
, ISBN: 92-64-01087-4
Available online at:
http://www.oecd-nea.org/nsd/reports/2006/nea6137-retour-experience.pdf
Other language(s):
- English:
Regulatory Challenges in Using Nuclear Operating Experience
La raison d'être des autorités de sûreté est de faire en sorte que les compagnies d'électricité exploitent leurs centrales nucléaires à tout moment de manière sûre. Pour atteindre cet objectif, l'expérience et ses enseignements se sont révélés précieux. Il est donc très important que tout exploitant nucléaire se dote d'un programme dynamique pour recueillir le retour d'expérience, analyser les informations intéressant la sûreté de ses centrales et prendre les mesures que dicte cette analyse.
Les experts de l'AEN ont constaté que la quasi-totalité des événements significatifs récents signalés lors de réunions internationales s'étaient déjà produits sous une forme ou sous une autre. Les contre-mesures sont généralement bien connues, mais l'information ne semble pas toujours parvenir aux utilisateurs finals, de même que les programmes d'actions correctrices ne sont pas toujours rigoureusement appliqués. Par conséquent, si l'on veut préserver l'excellent niveau de sûreté en exploitation obtenu à ce jour, il faut veiller à ce que le retour d'expérience soit communiqué sans délai aux systèmes établis de notification des événements, de préférence internationaux, pour que chacun puisse bénéficier d'une plus vaste expérience et que les enseignements qui en seront tirés soient effectivement exploités pour améliorer la sûreté.
Le présent rapport s'intéresse aux moyens dont disposent les autorités de sûreté pour s'assurer que le retour d'expérience est efficacement exploité pour améliorer la sûreté des centrales nucléaires. Bien que focalisé sur les centrales nucléaires, il énonce des principes qui s'appliquent également à d'autres installations nucléaires.
Regulatory Challenges in Using Nuclear Operating Experience
English
, 24 pages, published: 02/20/06
NEA#6159
, ISBN: 92-64-01083-1
Available online at:
http://www.oecd-nea.org/nsd/reports/2006/nea6159-operating-experience.pdf
Other language(s):
- Français:
L'utilisation du retour d'expérience : défis pour les autorités de sûreté nucléaire
The fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear utilities operate their plants in an acceptably safe manner at all times. Learning from experience has been a key element in meeting this objective. It is therefore very important for nuclear power plant operators to have an active programme for collecting, analysing and acting on the lessons of operating experience that could affect the safety of their plants.
NEA experts have noted that almost all of the recent, significant events reported at international meetings have occurred earlier in one form or another. Counter-actions are usually well-known, but information does not always seem to reach end users, or corrective action programmes are not always rigorously applied. Thus, one of the challenges that needs to be met in order to maintain good operational safety performance is to ensure that operating experience is promptly reported to established reporting systems, preferably international in order to benefit from a larger base of experience, and that the lessons from operating experience are actually used to promote safety.
This report focuses on how regulatory bodies can ensure that operating experience is used effectively to promote the safety of nuclear power plants. While directed at nuclear power plants, the principles in this report may apply to other nuclear facilities as well.
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La fonction réglementaire et la gestion des déchets radioactifs
Panorama international
Français
, 24 pages, published: 12/30/05
NEA#6042
, ISBN: 92-64-01076-9
Available online at:
http://www.oecd-nea.org/rwm/reports/2005/nea6042-fonction-reglementaire.pdf
Other language(s):
- English:
The Regulatory Function and Radioactive Waste Management 
Ce panorama présente un synopsis facile à aborder du contrôle réglementaire de la gestion des déchets radioactifs de 15 pays membres de l'AEN. Il traite la question de la gestion des déchets radioactifs issus de tous les types d'installations nucléaires, tels que les centrales nucléaires, les réacteurs de recherche et les installations du cycle du combustible. Il porte également sur les déchets radioactifs issus d'applications médicales, expérimentales, industrielles et, le cas échéant, militaires. Ce panorama devrait présenter un intérêt pour un large lectorat, comprenant des spécialistes aussi bien que des non-spécialistes.
Review of the Role, Activities and Working Methods of the CSNI
Committee on the Safety of Nuclear Installations (CSNI)
English
, 40 pages, published: 11/14/05
NEA#6032
, ISBN: 92-64-01072-6
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea6032-csni-role.pdf
This report, prepared by a senior-level assessment group, describes the current role, priorities and working methods of the NEA Committee on the Safety of Nuclear Installations (CSNI), identifies and analyses issues of concern, and suggests ways to further increase the efficiency and effectiveness of the committee. It also reviews CSNI interactions with the NEA Committee on Nuclear Regulatory Activities (CNRA), the other NEA standing technical committees and international organisations, and suggests ways to improve co-ordination and co-operation. In closing, conclusions are drawn and recommendations made concerning the future operation and role of the committee.
La sûreté du cycle du combustible nucléaire
Français
, 344 pages, published: 11/10/05
NEA#3589
, ISBN: 92-64-01423-3
Available online at:
http://www.oecd-nea.org/nsd/pubs/2005/3589-surete-cycle-combustible.pdf
Other language(s):
- English:
The Safety of the Nuclear Fuel Cycle
On distingue habituellement deux phases dans le cycle du combustible nucléaire, l'amont et l'aval, qui recouvrent respectivement l'extraction et la préparation du combustible destiné aux réacteurs de puissance nucléaires, puis, après son passage en réacteur, la récupération, le traitement et la gestion du combustible irradié. Les installations utilisées pour ces activités bénéficient depuis plus de 50 ans de dossiers de sûreté complets et rigoureux préparés par les spécialistes et autorités de sûreté. Ces mêmes dossiers ont permis une analyse en profondeur de l'ensemble du cycle du combustible.
Précédée par une première édition en 1981, et une deuxième en 1993, cette nouvelle édition de La sûreté du cycle du combustible nucléaire est une analyse de pointe en ce qui concerne la sûreté du cycle du combustible. Elle sera d'un grand intérêt non seulement pour les experts en sûreté nucléaire, mais aussi pour tous ceux qui souhaitent obtenir des informations complètes sur le cycle du combustible en général.
The Safety of the Nuclear Fuel Cycle
English
, 320 pages, published: 10/31/05
NEA#3588
, ISBN: 92-64-01421-7
Available online at:
http://www.oecd-nea.org/nsd/pubs/2005/3588-safety-nuclear-fuel-cycle.pdf
Other language(s):
- Français:
La sûreté du cycle du combustible nucléaire
The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the "front end" and "back end" of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle.
Preceded by two previous editions in 1981 and 1993, this new edition of the Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally.
La prise de décision en matière de réglementation nucléaire
Français
, 36 pages, published: 06/24/05
NEA#5357
, ISBN: 92-64-01052-1
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea5357-decision-fr.pdf
Other language(s):
- English:
Nuclear Regulatory Decision Making
L'objectif fondamental de toutes les autorités de sûreté nucléaire est de veiller à ce que les compagnies d'électricité qui exploitent des centrales nucléaires le fassent en permanence de manière acceptable sur le plan de la sûreté. Dans la réalisation de cet objectif, l'autorité de sûreté doit s'attacher à faire en sorte que ses décisions réglementaires soient techniquement bien fondées, cohérentes d'une affaire à une autre, et prises en temps voulu. En outre, l'autorité de sûreté doit être consciente du fait que ses décisions et le contexte dans lequel elles se situent, peuvent déterminer la manière dont ses interlocuteurs, par exemple les responsables de l'action gouvernementale, l'industrie qu'elle réglemente et le public, la considèrent, comme un organisme de réglementation efficace et crédible. Afin de conserver la confiance de ces interlocuteurs, l'autorité de sûreté devrait s'assurer que ses décisions sont transparentes, ont un fondement bien défini sur le plan juridique et réglementaire et sont considérées par des observateurs impartiaux comme étant équitables pour toutes les parties.
Basé sur les travaux d'un Groupe d'experts de l'Agence pour l'énergie nucléaire (AEN), ce rapport analyse certains principes et critères fondamentaux dont une autorité de sûreté devrait tenir compte dans la prise de décision et décrit les éléments d'un cadre de référence intégré pour la prise de décisions réglementaires.
Review of the Role, Activities and Working Methods of the CNRA
Committee on Nuclear Regulatory Activities (CNRA)
English
, 64 pages, published: 06/13/05
NEA#6028
, ISBN: 92-64-01062-9
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea6028-cnra-role.pdf
Other language(s):
- Français:
French version of the Review of the Role, Activities and Working Methods of the CNRA
This report, prepared by an independent review group, characterises the current role, priorities and working methods of the NEA Committee on Nuclear Regulatory Activities (CNRA), identifies and analyses issues of concern, and suggests ways to further increase the efficiency and effectiveness as well as the visibility of the committee. It also reviews the role and interactions between the CNRA and the other NEA standing technical committees and international organisations, and suggests ways to improve co-ordination and co-operation.
In formulating its report, the review group examined various CNRA documents (e.g. summary records, reports) interviewed past and present CNRA members, standing technical committee chairs and others, and gathered additional input through a questionnaire.
Conclusions and recommendations have been derived concerning the mid-term and long-term role and orientation of the committee and, in particular, the balance between technical- and policy-related activities.
Plan stratégique conjoint CSIN/CANR et mandats
2005-2009
Français
, 20 pages, published: 05/31/05
NEA#6035
, ISBN: 92-64-01061-0
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea6034-csni-cnra-stratplan-fr.pdf
Other language(s):
- English:
Joint CSNI/CNRA Strategic Plan and Mandates
Le Comité sur les activités nucléaires réglementaires (CANR) et le Comité sur la sûreté des installations nucléaires (CSIN) ont pour mission d'aider les pays membres à maintenir et à faire progresser les connaissances, les compétences et l'infrastructure nécessaires à l'exploitation sûre des centrales nucléaires et des installations du cycle du combustible tout au long du cycle de vie, ainsi qu'à leur réglementation efficiente et efficace en se fondant sur des informations techniques fiables, une expérience partagée et les méthodes les plus modernes.
Les lecteurs trouveront dans cette publication la mission, le plan stratégique et les mandats de ces comités.
Joint CSNI/CNRA Strategic Plan and Mandates
2005-2009
English
, 20 pages, published: 05/31/05
NEA#6034
, ISBN: 92-64-01060-2
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea6034-csni-cnra-stratplan.pdf
Other language(s):
- Français:
Plan stratégique conjoint CSIN/CANR et mandats
The mission of the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) is to assist member countries in maintaining and further developing the knowledge, competence and infrastructure needed to support the safe operation of nuclear power plants and fuel cycle facilities throughout their life cycle, as well as their efficient and effective regulation based upon sound technical information, shared experience and up-to-date methods.
Readers will find the committee's mission, joint strategic plan and mandates herein.
Nuclear Regulatory Decision Making
English
, 36 pages, published: 03/25/05
NEA#5356
, ISBN: 92-64-01051-3
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea5356-decision.pdf
Other language(s):
- Français:
La prise de décision en matière de réglementation nucléaire
The fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear utilities operate their plants at all times in an acceptably safe manner. In meeting this objective, the regulatory body should strive to ensure that its regulatory decisions are technically sound, consistent from case to case, and timely. In addition, the regulator must be aware that its decisions and the circumstances surrounding those decisions can affect how its stakeholders, such as government policy makers, the industry it regulates, and the public, view it as an effective and credible regulator. In order to maintain the confidence of those stakeholders, the regulator should make sure that its decisions are transparent, have a clear basis in law and regulations, and are seen by impartial observers to be fair to all parties.
Based on the work of a Nuclear Energy Agency (NEA) expert group, this report discusses some of the basic principles and criteria that a regulatory body should consider in making decisions and describes the elements of an integrated framework for regulatory decision making.
Avis techniques du CSIN - Nos 7-8
EPS vivante et son utilisation dans le processus décisionnel en matière de sûreté nucléaire - Mise au point et utilisation de l'EPS temps réel dans les centrales nucléaires
Français
, 40 pages, published: 02/01/05
NEA#4412
, ISBN: 92-64-01048-3
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea4412-EPS.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - Nos. 7-8
Dans de nombreuses centrales nucléaires dans le monde, les études probabilistes de sûreté (EPS) sont gérées comme des "EPS vivantes" les adaptant en fonction des modifications apportées à la conception et à l'exploitation de la centrale concernée, des progrès réalisés dans la compréhension des comportements de la centrale en situations de défaillance et des améliorations dans les méthodes, les modèles et les données relatifs aux EPS. Une EPS vivante peut notamment déboucher sur une EPS temps réel, utilisée par les exploitants et les autorités de sûreté pour obtenir des données sur les risques destinées à alimenter le processus décisionnel visant à assurer la sûreté d'exploitation des centrales nucléaires. Depuis que les premières EPS temps réel ont été mises en place en 1988, leur nombre a augmenté rapidement de telle sorte qu'à la fin de 2003 plus de 110 étaient opérationnelles, et que le cap des 150 devrait être franchi lorsque celles en cours de développement seront implémentées.
La réunion de ces deux avis techniques dans une publication unique met à la disposition de l'audience visée - à savoir ici les directeurs de recherche et les dirigeants dans l'industrie nucléaire, les autorités de sûreté nucléaire, les exploitants de centrales - un bilan concis de l'état d'avancement des connaissances leur permettant de mieux analyser la situation au moment d'évaluer des propositions ou les progrès accomplis dans les applications.
CSIN : Comité de l'AEN sur la sûreté des installations nucléaires.
CSNI Technical Opinion Papers - Nos. 7-8
Living PSA and its Use in the Nuclear Safety Decision-making Process - Development and Use of Risk Monitors at Nuclear Power Plants
English
, 40 pages, published: 02/01/05
NEA#4411
, ISBN: 92-64-01047-5
Available online at:
http://www.oecd-nea.org/nsd/reports/2005/nea4411-PSA-risk-monitors.pdf
Other language(s):
- Français:
Avis techniques du CSIN - Nos 7-8
Probabilistic safety analyses (PSAs) for many of the nuclear power plants throughout the world are being maintained as "living PSAs" (LPSAs), being updated to take account of changes to the design and operation of the plant, improvements in the understanding of how the plant behaves in fault situations and improved PSA methods, models and data. One of the specific applications of a living PSA is the risk monitor, used by operators and regulators to provide risk information employed in the decision-making process to ensure the safe operation of nuclear power plants. Since the first risk monitors were put into operation in 1988, the number of risk monitors worldwide has increased rapidly. By the end of 2003 there were more than 110 in operation and this figure should increase to over 150 when those monitors being developed are placed in service.
Combining these two technical opinion papers into a single publication provides the reader - notably senior researchers and industry leaders, nuclear safety regulators, nuclear power plant operators - with a concise assessment of the current state of the art, thus enabling better analysis when evaluating proposals or the development of these applications.
CSNI: NEA Committee on the Safety of Nuclear Installations.
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Le facteur humain : un défi pour les autorités de sûreté nucléaire
Français
, 24 pages, published: 12/02/04
NEA#5335
, ISBN: 92-64-02090-X
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5335-facteur-humain.pdf
Other language(s):
- English:
Nuclear Regulatory Challenges Related to Human Performance
En juin 2003, le Comité sur les activités nucléaires réglementaires (CANR) de l'Agence de l'OCDE pour l'énergie nucléaire (AEN) a organisé un débat sur l'importance, pour la sûreté nucléaire, du facteur humain et des facteurs d'influence y afférents. La discussion a porté sur trois questions principales :
- Le facteur humain est-il aussi important pour la sûreté des installations nucléaires que semblent l'indiquer de nombreuses sources ?
- L'importance du facteur humain s'est-elle accrue au cours des cinq à dix dernières années ?
- Quelles recommandations peut-on formuler concernant la gestion des défis liés au facteur humain ?
Cette publication présente un résumé des présentations d'introduction ainsi qu'une description des défis réglementaires identifiés durant les discussions. L'audience visée est en premier lieu les autorités de sûreté nucléaire ; les organisations de soutien technique, les exploitants de centrales nucléaires, les autorités gouvernementales et le public pourront aussi être intéressés.
CSNI Technical Opinion Papers - No. 6
PSA-based Event Analysis
English
, 24 pages, published: 12/02/04
NEA#4409
, ISBN: 92-64-02091-8
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea4409-PSA.pdf
Other language(s):
- Français:
Avis techniques du CSIN - No 6
This technical opinion paper provides the reader with a concise description of both the benefits and disadvantages of using probabilistic safety assessment (PSA) to analyse operational events in nuclear power plants in order to facilitate better operator feedback. The paper's objective is to present decision makers in the nuclear field with a clear technical opinion on how PSA techniques can be used to address this issue. The intended audience is primarily nuclear safety regulators, senior researchers and industry leaders. Government authorities, nuclear power plant operators and the general public may also be interested.
CSNI: NEA Committee on the Safety of Nuclear Installations.
Nuclear Regulatory Challenges Related to Human Performance
English
, 24 pages, published: 12/02/04
NEA#5334
, ISBN: 92-64-02089-6
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5334-human-performance.pdf
Other language(s):
- Français:
Le facteur humain : un défi pour les autorités de sûreté nucléaire
In June 2003, the OECD Nuclear Energy Agency (NEA) Committee on Nuclear Regulatory Activities (CNRA) organised a topical session on the importance of human performance to nuclear safety and the factors influencing it. The discussion focused on three questions:
- Is human performance as important to the safety of nuclear installations as many references seem to indicate?
- Has the importance of human performance increased during the past five to ten years?
- What recommendations can be made on how to manage human peformance challenges?
This publication provides a summary of the introductory presentations as well as a description of the regulatory challenges identified during the discussions. The publication's intended audience is primarily nuclear regulators; it may also be of interest to technical support organisations, nuclear operators, governmental bodies and the general public.
Avis techniques du CSIN - No 6
Analyse d'événements fondée sur l'EPS
Français
, 24 pages, published: 12/02/04
NEA#4410
, ISBN: 92-64-01045-9
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea4410-EPS.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 6
Le présent avis technique offre au lecteur une description concise des avantages et des inconvénients de l'utilisation de l'évaluation probabiliste de la sûreté (EPS) dans l'analyse des événements d'exploitation des centrales nucléaires en vue de faciliter un meilleur retour d'expérience en matière d'exploitation. Il s'agit de présenter aux responsables nucléaires un point de vue technique clair sur l'utilisation des EPS sur ce sujet. L'audience visée est donc en premier lieu les autorités de sûreté nucléaire, les responsables de la recherche et les industriels. Les autorités gouvernementales, les exploitants de centrales nucléaires et le grand public pourraient aussi être intéressés.
CSIN : Comité de l'AEN sur la sûreté des installations nucléaires.
Debris Impact on Emergency Coolant Recirculation
Workshop Proceedings, Albuquerque, NM, USA, 25-27 February 2004
English
, 424 pages, published: 10/29/04
NEA#5468
, ISBN: 92-64-00666-4
Available online at:
http://www.oecd-nea.org/nsd/pubs/2004/5468-debris-impact.pdf
Under normal operation, nuclear reactor fuel is cooled by water circulating in the primary circuit. In the case of a loss-of-coolant accident, the reactor is stopped automatically. Residual fuel heat must then be evacuated, typically by use of a safety injection system and a reactor containment spray system. These systems are fed with water recovered from the bottom of the containment through sumps. However, because this water may contain debris (insulating material, concrete particles, paint), sumps are equipped with strainers. These strainers may become clogged, preventing emergency coolant recirculation. This could in turn lead to reactor core overheating, or melting in the most extreme cricumstances.
Participants at the workshop discussed the most recent research and developments in this field, as well as proposed and implemented solutions. These proceedings contain the papers presented at the workshop as well as a summary of the discussions that took place.
CSNI Technical Opinion Papers - No. 5
Managing and Regulating Organisational Change in Nuclear Installations
English
, 20 pages, published: 06/09/04
NEA#5348
, ISBN: 92-64-02069-1
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5348-change.pdf
Other language(s):
- Français:
Avis techniques du CSIN - N° 5
Nuclear licensees are increasingly required to adapt to a more challenging commercial environment as electricity markets are liberalised. One of the costs that is often perceived as being amenable to control is staffing, and hence there is significant exploration of new strategies for managing this cost - for example, by reducing staffing levels, changing organisational structures, adopting new shift strategies, introducing new technology or increasing the proportion of work carried out by external contractors. However, if changes to staffing levels or organisational structures and systems are inadequately conceived or executed they have the potential to affect the way in which safety is managed.
In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Special Expert Group on Human and Organisational Factors (SEGHOF) organised an international workshop to discuss the management and regulation of organisational change in 2001. This technical opinion paper distils the findings of that workshop and sets out the factors that regulatory bodies might reasonably expect to be addressed within licensees' arrangements to manage organisational change. The paper should be of particular interest to both regulators and managers of nuclear utilities.
Avis techniques du CSIN - N° 5
Gestion et réglementation des changements organisationnels dans les installations nucléaires
Français
, 24 pages, published: 06/09/04
NEA#5349
, ISBN: 92-64-02070-5
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5349-changements.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 5
L'ouverture des marchés de l'électricité, et l'environnement de plus en plus concurrentiel qui en découle, exigent des exploitants nucléaires une adaptabilité toujours plus grande. Les charges de personnel étant souvent perçues comme maîtrisables, c'est vers la recherche de nouvelles stratégies pour gérer ce poste que porte le gros de l'effort. Il s'agit notamment de la réduction des effectifs, du changement des structures organisationnelles, de la réorganisation du travail posté, de l'introduction de nouvelles technologies ou du recours plus sytématique à la sous-traitance. Cependant, toute erreur dans la conception ou la mise en œuvre des changement d'effectifs ou de structure et de systèmes organisationnels est susceptible de se répercuter sur la gestion de la sûreté.
Dans ce contexte, le Comité de l'AEN sur la sûreté des installations nucléaires (CSIN) et son Groupe spécial sur les facteurs humains et organisationnels (SEGHOF) ont organisé en 2001 un atelier international consacré à la gestion et à la réglementation du changement organisationnel. Le présent avis technique analyse les conclusions de cet atelier et en dégage les facteurs que les autorités de sûreté pourraient espérer voir abordés par les exploitants dans le cadre des dispositifs qu'ils mettent en place pour gérer le changement organisationnel. Cet avis technique s'adresse principalement aux autorités de sûreté nucléaire et aux chefs d'installations nucléaires.
Indicateurs directs de l'efficience et de l'efficacité de la réglementation nucléaire
Résultats du projet pilote
Français
, 52 pages, published: 04/20/04
NEA#3670
, ISBN: 92-64-02062-4
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea3669-indicateurs.pdf
Other language(s):
- English:
Direct Indicators of Nuclear Regulatory Efficiency and Effectiveness
Le résultat escompté des activités nucléaires réglementaires est d'assurer que les installations nucléaires sont exploitées dans des conditions de sûreté qui préservent la santé et la sécurité du public et l'environnement. La responsabilité première d'une exploitation sûre incombe à l'exploitant ; cependant, l'action de l'autorité de sûreté contribue à la réalisation de cet objectif.
Un groupe de travail a été créé par le Comité de l'AEN sur les activités nucléaires réglementaires (CANR) afin de développer un ensemble d'indicateurs de performance directs de l'efficience et de l'efficacité réglementaires. Ce rapport décrit les résultats du projet pilote réalisé par le groupe afin de tester les indicateurs développés, formule quelques observations générales quant à l'utilité d'indicateurs individuels et fait des recommandations d'activités futures. Il s'adresse essentiellement aux autorités de sûreté nucléaire, mais pourrait également intéresser des représentants des instances gouvernementales, des exploitants de centrales nucléaires et le grand public.
Direct Indicators of Nuclear Regulatory Efficiency and Effectiveness
Pilot Project Results
English
, 48 pages, published: 04/20/04
NEA#3669
, ISBN: 92-64-02061-6
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea3669-indicators.pdf
Other language(s):
- Français:
Indicateurs directs de l'efficience et de l'efficacité de la réglementation nucléaire
The desired outcome of nuclear regulatory activities is the safe operation of nuclear facilities in a manner that protects public health and safety, and the environment. The operator has prime responsibility for safe operation; however, the actions of the regulator contribute to this objective.
A task group was established by the NEA Committee on Nuclear Regulatory Activities (CNRA) to develop a set of direct performance indicators of regulatory efficiency and effectiveness. This report describes the pilot project carried out by the task group to test the indicators developed, and makes some general observations about the usefulness of individual indicators as well as recommendations for future activities. While primarily directed at nuclear safety regulators, the report may also be of interest to government authorities, nuclear power plant operators and the general public.
Déclaration collective concernant la recherche sur la sûreté nucléaire
Moyens et compétences techniques au profit de l'efficience et de l'efficacité du contrôle réglementaire des centrales nucléaires
Français
, 20 pages, published: 03/26/04
NEA#5491
, ISBN: 92-64-02060-8
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5491-recherche.pdf
Other language(s):
- English:
Collective Statement Concerning Nuclear Safety Research
L'ampleur des recherches financées par les autorités de sûreté pour leur activités réglementaires varie d'un pays à l'autre. Cette opinion collective expose l'intérêt pour la sûreté ainsi que pour l'efficacité et l'efficience du contrôle réglementaire de préserver des moyens et des compétences techniques de recherche en sûreté. Elle pourra guider les pays membres de l'AEN dans leur réflexion sur les moyens et les compétences qu'il convient de sauvegarder et pour quelles raisons. Bien qu'elle soit destinée avant tout à être lue par les directeurs de recherche, les autorités de sûreté et les centres de recherche, elle pourra aussi intéresser les organismes publics, les exploitants de centrales nucléaires et le grand public.
Collective Statement Concerning Nuclear Safety Research
Capabilities and Expertise in Support of Efficient and Effective Regulation of Nuclear Power Plants
English
, 20 pages, published: 03/26/04
NEA#5490
, ISBN: 92-64-02169-8
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5490-research.pdf
Other language(s):
- Français:
Déclaration collective concernant la recherche sur la sûreté nucléaire
The degree to which regulatory-sponsored nuclear safety research is conducted and utilised in the regulatory process varies from country to country. This statement articulates the value to efficient and effective regulation, as well as to safety, of maintaining safety research capability and expertise. It can serve as a guideline for consideration by NEA member countries in determining what safety research capability and expertise should be maintained in support of regulation and why. The intended readership is primarily nuclear safety research managers, regulatory organisations and research centres. Government authorities, nuclear power plant operators and the general public may also be interested.
CSNI Technical Opinion Papers - No. 4
Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants
English
, 20 pages, published: 02/09/04
NEA#5068
, ISBN: 92-64-02157-4
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5068-HRA.pdf
Other language(s):
- Français:
Avis techniques du CSIN - No 4
This technical opinion paper represents the consensus of risk analysts in NEA member countries on the current state of the art of human reliability analysis (HRA) in probabilistic safety assessment (PSA) for nuclear power plants. The paper's objective is to present decision makers in the nuclear field with a clear technical opinion on HRA status as implemented in industrial PSAs. The intended audience is primarily nuclear safety regulators, senior researchers and industry leaders. Government authorities, nuclear power plant operators and the general public may also be interested.
CSNI: NEA Committee on the Safety of Nuclear Installations.
Avis techniques du CSIN - No 4
L'évaluation probabiliste de la fiabilité humaine dans les centrales nucléaires
Français
, 20 pages, published: 02/09/04
NEA#5069
, ISBN: 92-64-02158-2
Available online at:
http://www.oecd-nea.org/nsd/reports/2004/nea5069-EPFH.pdf
Cet avis technique représente l'opnion des analystes des risques des pays membres de l'AEN sur l'état actuel de l'analyse de la fiabilité humaine dans les études probabilistes de sûreté (EPS) des centrales nucléaires. Il s'agit d'offrir aux responsables nucléaires un point de vue technique clair sur la situation de l'analyse de la fiabilité humaine telle qu'elle est utilisée dans les EPS industrielles. Cet avis s'adresse principalement aux autorités de sûreté nucléaire, aux directeurs de recherche et aux dirigeants d'entreprises, mais il pourra également intéresser les autorités publiques, les exploitants de centrales nucléaires ainsi que le grand public.
CSIN : Comité de l'AEN sur la sûreté des installations nucléaires.
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CSNI Technical Opinion Papers - No. 3
Recurring Events
English
, 20 pages, published: 12/31/03
NEA#4388
, ISBN: 92-64-02155-8
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4388-recurring.pdf
Other language(s):
- Français:
Avis techniques du CSIN - No 3
Feedback on operating experience from nuclear power plants is intended to help avoid occurrence or recurrence of safety-significant events. Well-established feedback systems exist on the national and international levels. One such example is the Incident Reporting System (IRS), jointly operated by the International Atomic Energy Agency (IAEA) and the OECD Nuclear Energy Agency (NEA).
This technical opinion paper presents the international systems used to collect operating experience, the role of recurring events within them, examples of recurrence and ideas about how to improve the situation. It is expected that managers in both nuclear utilities and regulatory bodies, persons involved in operating experience feedback and analysis, inspectors and technical support organisation staff will be interested in this publication.
CSNI: NEA Committee on the Safety of Nuclear Installations.
Collective Statement Concerning Nuclear Safety Research
Good Practice and Closure Criteria
English
, 20 pages, published: 12/31/03
NEA#4908
, ISBN: 92-64-02149-3
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4908-closure.pdf
Other language(s):
- Français:
Déclaration collective concernant la recherche sur la sûreté nucléaire
The method for setting nuclear safety research priorities and the criteria for ranking programmes and projects, including for their closure, vary from one country to another. This collective statement addresses good practices in conducting nuclear safety research and focuses on closure considerations. It also considers the effects that closure can have for regulators and the industry, including potential losses of technical capability, expertise and facilities. The intended readership is primarily research managers, regulatory organisations and research centres. Government authorities, nuclear power plant operators and the general public may also be interested.
Déclaration collective concernant la recherche sur la sûreté nucléaire
Bonnes pratiques et critères d'arrêt
Français
, 20 pages, published: 12/31/03
NEA#4909
, ISBN: 92-64-02150-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4909-recherche.pdf
Other language(s):
- English:
Collective Statement Concerning Nuclear Safety Research
Chaque pays possède sa propre méthode pour fixer ses priorités de recherche en matière de sûreté nucléaire et ses critères spécifiques pour hiérarchiser ses programmes et projets, et éventuellement y mettre fin. La présente déclaration collective concerne les bonnes pratiques dans l'exécution des recherches en matière de sûreté nucléaire et met en lumière les conditions pouvant conduire à mettre un terme à une activité. Elle examine également les conséquences que pourrait entraîner une telle décision pour les autorités de sûreté et pour l'industrie, notamment les détriments éventuels en termes de moyens techniques, de compétences et d'installations de recherche. Cette déclaration s'adresse en premier lieu aux directeurs de recherche, aux autorités de sûreté et aux centres de recherche. Elle pourra aussi intéresser les autorités gouvernementales, les exploitants de centrales nucléaires et le grand public.
Avis techniques du CSIN - No 3
Evénements récurrents
Français
, 20 pages, published: 12/31/03
NEA#4389
, ISBN: 92-64-02156-6
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4389-recurrent.pdf
Other language(s):
- English:
CSNI Technical Opinion Papers - No. 3
Le retour d'expérience des centrales nucléaires doit servir à éviter les événements importants pour la sûreté et leur répétition. Il existe aujourd'hui des systèmes bien établis de retour d'expérience aux niveaux national et international. Le Système de notification des incidents (IRS) que gèrent ensemble l'Agence internationale de l'énergie atomique (AIEA) et l'Agence de l'OCDE pour l'énergie nucléaire (AEN) en est un exemple.
Cet avis technique décrit les systèmes internationaux mis en place pour recueillir le retour d'expérience et la place qui y est réservée aux événements récurrents, des exemples d'événements récurrents ainsi que des propositions pour améliorer la situation. Cette publication devrait intéresser les exploitants de centrales nucléaires aussi bien que les autorités de sûreté, les spécialistes du recueil et de l'analyse du retour d'expérience, les inspecteurs et le personnel des organismes d'appui technique.
CSIN : Comité de l'AEN sur la sûreté des installations nucléaires.
Nuclear Power Plant Operating Experiences from the IAEA/NEA Incident Reporting System
1999-2002
English
, published: 12/16/03
NEA#5168
Available online at:
http://www.oecd-nea.org/nsd/reports/nea5168-IRS.pdf
Incident reporting has become an increasingly important aspect of the operation and regulation of all public health and safety-related industries. Diverse industries such as aeronautics, chemicals, pharmaceuticals and explosives all depend on operating experience to provide lessons learnt about safety.
The Incident Reporting System (IRS) is an essential element of the system for feeding back international operating experience for nuclear power plants. IRS reports contain information on events of safety significance with important lessons learnt. These experiences assist in reducing or eliminating recurrence of events at other plants. The IRS is jointly operated and managed by the Nuclear Energy Agency and the International Atomic Energy Agency (IAEA).
The first report, which covered the period July 1996-June 1999, was widely acclaimed and encouraged both agencies to prepare this second report in order to highlight important lessons learnt from around 300 events reported to the IRS for the period July 1999-December 2002. Several areas were selected in this report to show the range of important topics available in the IRS. These include different types of failure in a variety of plant systems, as well as human performance considerations.
This report is primarily aimed at senior officials in industry and government who have decision-making roles in the nuclear power industry.
Nuclear Regulatory Review of Licensee Self-assessment (LSA)
English
, 52 pages, published: 06/30/03
NEA#4728
, ISBN: 92-64-02132-9
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4728-lsa.pdf
Other language(s):
- Français:
Examen par les autorités de réglementation nucléaire des auto-évaluations par l'exploitant
Licensee self-assessment (LSA) by nuclear power plant operators is described as all the activities that a licensee performs in order to identify opportunities for improvements. An LSA is part of an organisation's holistic management system, which must include other process elements. Particularly important elements are: a process for choosing which identified potential improvements should be implemented and a process of project management for implementing the improvements chosen. Nuclear regulators expect the licensee to run an effective LSA programme, which reflects the licensee's "priority to safety".
Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publicaiton provides an overview of the current regulatory philosophy on and approaches to LSA as performed by licensees. The publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested.
Examen par les autorités de réglementation nucléaire des auto-évaluations par l'exploitant
Français
, 56 pages, published: 06/30/03
NEA#4729
, ISBN: 92-64-02133-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4729-auto-eval.pdf
Other language(s):
- English:
Nuclear Regulatory Review of Licensee Self-assessment (LSA)
Par auto-évaluation par l'exploitant (LSA) de centrales nucléaires, on entend toutes les activités que l'exploitant mène afin de cerner les possibilités d'améliorations. Ce type d'auto-évaluation s'nscrit dans le cadre du système de gestion holistique d'une organisation, qui doit inclure d'autres types de processus. Parmi ceux revêtant une importance particulière figurent un processus permettant de choisir les améliorations potentielles recensées auxquelles il convient de donner suite et un processus de gestion du projet pour la mise en oeuvre des améliorations. Les autorités de sûreté attendent des exploitants qu'ils appliquent un programme efficace d'auto-évaluation, qui témoigne de la "priorité accordée à la sûreté".
Sur la base des contributions émanant des membres du Comité de l'AEN sur les activités nucléaires réglementaires (CANR), la présente publication donne un aperçu de la philosophie et des méthodes réglementaires actuelles concernant les auto-évaluations telles qu'elles sont appliquées par les titulaires d'autorisation. Cette publication s'adresse avant tout aux autorités de sûreté nucléaire, mais elle pourra aussi intéresser les autorités publiques, les exploitants de centrales nucléaires et le grand public.
Coopération autorités de sûreté-industrie pour la recherche en sûreté nucléaire
Défis et potentialités
Français
, 48 pages, published: 05/27/03
NEA#4688
, ISBN: 92-64-02127-2
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4688-recherche.pdf
Other language(s):
- English:
Regulator and Industry Co-operation on Nuclear Safety Research
La coopération entre les autorités de sûreté et l'industrie dans le domaine de la recherche sur la sûreté nucléaire peut avoir des avantages comme des inconvénients. Ce rapport fournit aux responsables de recherche de l'industrie, des organismes de sûreté et des centres de recherche des informations sur les pratiques actuelles dans les pays membres de l'OCDE en matière de partenariat de recherche sur la sûreté. Il décrit les moyens permettant d'instaurer une collaboration efficace entre les autorités de sûreté et l'industrie et donne des indications sur la manière de surmonter les difficultés que pourrait soulever ce type de collaboration. Il formule aussi des avis sur les éventuels sujets de préoccupation. Le rapport se penche notamment sur le problème de l'indépendance des autorités de sûreté, ainsi que sur les moyens de la préserver et de la démontrer au public en cas de collaboration avec l'industrie.
Regulator and Industry Co-operation on Nuclear Safety Research
Challenges and Opportunities
English
, 46 pages, published: 05/27/03
NEA#4413
, ISBN: 92-64-02126-4
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4413-research.pdf
Other language(s):
- Français:
Coopération autorités de sûreté-industrie pour la recherche en sûreté nucléaire
Regulator-industry co-operation in nuclear safety research has potential advantages as well as disadvantages. This report provides research managers in industry, regulatory organisations and research centres with information on current practices in collaborative safety research in OECD member countries. It identifies means of establishing effective industry-regulator collaboration and provides indications on how to overcome difficulties that can arise. It also advises on possible areas of concern. The report addresses in particular the issue of regulator independence, means to preserve it and ways to demonstrate it to the public while undertaking collaboration with industry.
Les autorités de sûreté face au démantèlement des réacteurs nucléaires
Français
, 32 pages, published: 04/30/03
NEA#4668
, ISBN: 92-64-02121-3
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4668-demantelement.pdf
Other language(s):
- English:
The Regulatory Challenges of Decommissioning Nuclear Reactors
Toute installation nucléaire aujourd'hui en exploitation, qu'il s'agisse d'une centrale, d'une usine du cycle du combustible ou d'une installation de recherche et d'essai, atteindra un jour la fin de sa vie utile et cessera de fonctionner. Pendant son démantèlement, il importe de gérer convenablement les risques pour la santé et l'environnement ainsi que les mesures de protection de l'installation à l'arrêt afin de préserver la santé et la sécurité des populations et des travailleurs, mais aussi de protéger toutes les matières nucléaires. Il revient à l'autorité de sûreté de s'assurer de son côté que le démantèlement est mené dans des conditions sûres, que les substances radioactives et le combustible nucléaire usé sont éliminés selon les règles et que le site se trouve dans un état final acceptable.
Le présent rapport a pour objet de décrire l'éventail des problèmes qui risquent de se poser pendant ces opérations, qu'il s'agisse de sûreté, d'environnement, d'organisation, de facteurs humains ou de politique publique, et que l'autorité de sûreté doit se préparer à résoudre dans le cadre de son dispositif réglementaire général. Il s'adresse en premier lieu aux autorités de sûreté, sachant que les informations et idées qu'il contient peuvent également intéresser les autorités pubiques et environnementales, les exploitants nucléaires, les organismes techniques et le grand public.
The Regulatory Challenges of Decommissioning Nuclear Reactors
English
, 32 pages, published: 04/30/03
NEA#4375
, ISBN: 92-64-02120-5
Available online at:
http://www.oecd-nea.org/nsd/reports/nea4375-decommissioning.pdf
Other language(s):
- Français:
Les autorités de sûreté face au démantèlement des réacteurs nucléaires
Each nuclear power plant, fuel cycle facility and nuclear research and test facility that is operating today will eventually reach the end of its useful life and cease operation. During the period of its decommissioning, it is important to properly manage the health and environmental hazards and physical protection measures of the shutdown facility in order to protect the health and safety of the public and workers and to safeguard any nuclear materials. In this regard, the nuclear safety regulatory body is responsible for independently assuring that decommissioning activities are conducted safely, that radioactive materials and spent nuclear fuel are disposed of properly and that the site is in an acceptable end state.
The purpose of this report is to describe the broad range of safety, environmental, organisational, human factors and public policy issues that may arise during the decommissioning of nuclear reactors and that the regulatory body should be prepared to deal with in the framework of its national regulatory system. The intended audience is primarily nuclear regulators, although the information and ideas may also be of interest to government authorities, environmental regulators, nuclear operating organisations, technical expert organisations and the general public.
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Improving Versus Maintaining Nuclear Safety
English
, 36 pages, published: 10/15/02
NEA#3672
, ISBN: 92-64-18493-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3672-improving.pdf
Other language(s):
- Français:
Améliorer ou maintenir le niveau de sûreté nucléaire
The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted.
Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested.
Améliorer ou maintenir le niveau de sûreté nucléaire
Français
, 36 pages, published: 10/15/02
NEA#3673
, ISBN: 92-64-28493-1
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3673-improving-fr.pdf
Maintenir ou améliorer le niveau de sûreté nucléaire : ce concept a souvent été discuté lors de réunions d'autorités de sûreté nucléaire dans les dernières années. Des rapports nationaux indiquent que des différences de philosophie existent parmi les pays membres de l'AEN dans leur approche réglementaire vis-à-vis des exigences faites aux exploitants de toujours maintenir ou toujours améliorer la sûreté nucléaire. Alors que le niveau de sûreté est globalement le même dans tous les pays membres, la conclusion est qu'il est très difficile de le quantifier. En pratique, toutes les approches réglementaires demandent que les améliorations soient apportées pour corriger des carences ou quand elles sont justifiées.
Cette publication, basée sur les contributons des pays membres du Comité de l'AEN sur les activités nucléaires réglementaires (CANR), apporte une vue d'ensemble des approches et des philosophies en pratique actuellement dans le domaine de la réglementation, ainsi que des considérations sur quelques questions liées à la perception par le public. Ce rapport vise principalement les autorités de sûreté nucléaire ; les autorités gouvernementales, les exploitants de centrales nucléaires et le public pourraient également être intéressés.
CSNI Technical Opinion Papers - Nos. 1-2
Fire Probabilistic Safety Assessment for Nuclear Power Plants
Seismic Probabilistic Safety Assessment for Nuclear Facilities
English
, 28 pages, published: 09/26/02
NEA#3948
, ISBN: 92-64-18490-2
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3948-fire-seismic.pdf
Other language(s):
- Français:
Avis techniques du CSIN - N° 1 et 2
These technical opinion papers represent the consensus of risk analysts and experts in NEA Member countries on the current state of the art in Fire Probabilistic Safety Assessment (PSA) for nuclear power plant design and operation and Seismic PSA for nuclear facilities. The objective is to present clear technical opinions to decision makers in the nuclear community. As such, the intended audience is primarily nuclear safety regulators, senior researchers and industry leaders. Government authorities, nuclear power plant operators and the general public may also be interested.
CSNI: NEA Committee on the Safety of Nuclear Installations.
Avis techniques du CSIN - N° 1 et 2
Etude probabiliste de sûreté-incendie des centrales nucléaires - Etude probabiliste de sûreté-séisme des installations nucléaires
Français
, 28 pages, published: 09/26/02
NEA#3949
, ISBN: 92-64-28490-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3948-fire-seismic-fr.pdf
Ces avis techniques présentent le consensus atteint par les analystes des risques et les experts des pays Membres de l'AEN sur l'état de l'art acutel des études probabilistes de sûreté (EPS)-incendie pour la conception et l'exploitation des centrales nucléaires, et des EPS-séisme pour les installations nucléaires. L'objectif est de présenter clairement les opinions techniques aux décideurs de la communuauté nucléaire. L'audience visée est donc en premier lieu, les autorités de sûreté nucléaire, les responsables de la recherche et les industriels. Les autorités gouvernementales, les exploitants de centrales nucléaires et le public peuvent aussi être intéressés.
CSIN : Comité de l'AEN sur la sûreté des installations nucléaires.
The Nuclear Regulatory Challenge of Judging Safety Backfits
English
, 24 pages, published: 06/14/02
NEA#3674
, ISBN: 92-64-18484-8
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3674-backfits.pdf
Other language(s):
- Français:
Juger les mises en conformité en matière de sûreté : un défi au plan réglementaire
The economic pressures of electricity market competition have led nuclear power plant operators to seek ways to increase electricity production and to reduce operating costs at their plants. Corresponding pressures on the regulatory bodies include operator demande to reduce regulatory burdens perceived as unnecessary and general resistance to consider safety backfits sought by the regulator.
The purpose of this report is to describe potential situations giving rise to safety backfit questions and to discuss regulatory approaches for judging the backfits.
The intented audience for this report is primarily nuclear regulators, although the information and ideas may also be of interest to nuclear operating organisations, other industry organisations and the general public.
Juger les mises en conformité en matière de sûreté : un défi au plan réglementaire
Français
, 28 pages, published: 06/14/02
NEA#3675
, ISBN: 92-64-28484-2
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3675-backfits-fr.pdf
Other language(s):
- English:
The Nuclear Regulatory Challenge of Judging Safety Backfits
Les pressions économiques de la concurrence sur le marché de l'électricité ont conduit les exploitants de centrales nucléaires à rechercher des moyens d'accroître la production d'électricité et de réduire les coûts d'exploitation dans leurs centrales. Ces pressions se traduisent par des contraintes sur les organismes de réglementation, au nombre desquelles figurent le souhait des exploitants de réduire les exigences réglementaires perçues comme superflues et une résistance de ces derniers à envisager les mises en conformité en matière de sûreté voulues par l'autorité de sûreté.
Le présent rapport a pour objet de décrire les situations qui peuvent donner lieu à des questions de mise en conformité en matière de sûreté et d'examiner les démarches réglementaires adoptées pour juger ces mises en conformité.
Ce rapport s'adresse avant tout aux autoirtés de sûreté nucléaire, bien que les informations et idées présentées puissent aussi intéresser des exploitants nucléaires, d'autres organisations de l'industrie et le grand public.
Advanced Nuclear Safety Issues and Research Needs
Workshop Proceedings, Paris, France, 18-20 February 2002
English
, 344 pages, published: 05/29/02
NEA#3613
, ISBN: 92-64-19781-8
Available online at:
http://www.oecd-nea.org/nsd/pubs/2002/3613-advanced-safety-issues.pdf
New nuclear reactor designs are expected to have a higher level of safety than current designs. As part of the efforts to achieve this, important safety issues related to the new designs need to be identified at an early stage, and research required for problem resolution defined.
These proceedings bring together the papers presented at the OECD/NEA Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Conclusions of the workshop discussions are offered at the end of the book, which will be of particular interest to all those involved in planning and designing the next generation of nuclear reactors.
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Nuclear Fuel Safety Criteria Technical Review
English
, 68 pages, published: 12/05/01
NEA#3349
, ISBN: 92-64-19687-0
Available online at:
http://www.oecd-nea.org/nsd/pubs/2001/3349-safety-criteria-technical-review.pdf
Nuclear reactor safety is primarily concerned with the prevention of radiation-related damage to the public from the operation of commercial nuclear reactors; safety limits are introduced to avoid fuel failures during normal operation, or to mitigate the consequences of reactor accidents in which substantial damage is done to the reactor core.
In this report, brief descriptions of 20 fuel-related safety criteria are presented along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them. No attempt was made to categorise the criteria according to event type or risk significance.
This report will be of particular interest to nuclear engineers working in the area of fuel safety and to all those interested in general aspects of nuclear safety.
Examen des critères techniques de sûreté du combustible nucléaire
Français
, 78 pages, published: 12/04/01
NEA#3368
, ISBN: 92-64-29687-5
Available online at:
http://www.oecd-nea.org/nsd/pubs/2001/3368-fuel-safety-criteria-review-FR.pdf
La sûreté des réacteurs nucléaires concerne au premier chef la prévention des dommages qui pourraient résulter de l'exposition du public aux rayonnements liés à l'exploitation des réacteurs nucléaires de type industriel. L'introduction de limites de sûreté vise à éviter des défaillances du combustible en cours d'exploitation normale ou à atténuer les conséquences d'accidents de réacteur au cours desquels des dommages substantiels pourraient être causés au coeur du réacteur.
On trouvera dans le présent rapport de brèves descriptions de 20 critères de sûreté liés au combustible, ainsi qu'un exposé de leur raison d'être et des questions éventuelles liées aux nouveaux concepts et à leur exploitation, qui pourraient avoir une incidence sur ces critères. On n'a pas cherché à classer les critères en fonction d'un type d'événement ou de l'importance du risque.
Le présent rapport s'adresse en particulier aux ingénieurs nucléaires travaillant sur la sûreté du combustible ainsi qu'à toute personne intéressée par les aspects généraux de la sûreté nucléaire.
Maintenir à l'avenir les compétences de sûreté nucléaire
Mesures spécifiques
Francais
, 72 pages, published: 07/20/01
NEA#3147
, ISBN: 92-64-28461-1
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3147-competencies.pdf
Dans plusieurs pays, les experts de sûreté nucléaire qui partent à la retraite ne sont pas remplacés par des équivalents plus jeunes. Ceci risque de provoquer une pénurie d'experts nécessaires pour assurer la régulation effective de l'industrie nucléaire. Ceci pourrait également mener à la perte d'une fraction importante des connaissances actuelles en matière de sûreté nucléaire. Le rapport examine des moyens spécifiques pour maintenir à l'avenir les compétences de sûreté nucléaire des autorités de sûreté et de l'industrie.
Nuclear Safety Research in OECD Countries
Major Facilities and Programmes at Risk
English
, 158 pages, published: 05/23/01
NEA#3145
, ISBN: 92-64-18468-6
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3145-safetyresearch.pdf
Major nuclear safety research facilities and programmes are facing increasing budgetary constraints, and in many cases are being closed or terminated. This report identifies major facilities of vital interest to the international nuclear safety community and makes recommendations for their continued operation in an international framework, either as joint projects or centres of excellence.
Investing in Trust: Nuclear Regulators and the Public
Workshop Proceedings, Paris, France, 29 November-1st December 2000
English
, 324 pages, published: 05/16/01
NEA#3062
, ISBN: 92-64-19314-6
Available online at:
http://www.oecd-nea.org/nsd/pubs/2001/3062-investing-in-trust.pdf
Good governance and efficiency in decision making by governmental authorities are increasingly dependent upon mutual trust and confidence between those authorities and the public. This workshop provided an opportunity to exchange information and views on how national nuclear regulatory organisations can improve their interface with the public.
Améliorer l'efficacité des autorités de sûreté nucléaire
Francais
, 50 pages, published: 05/03/01
NEA#3149
, ISBN: 92-64-28465-6
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3149-efficacite.pdf
Other language(s):
- English:
Improving Nuclear Regulatory Effectiveness
Faire en sorte que les installations nucléaires soient exploitées et entretenues de façon à réduire au minimum réalisable leur impact sur la santé humaine et la sûreté, tel a toujours été l'objectif premier de la réglementation nucléaire. Dans le passé, les incidents nucléaires ont été à la base des améliorations de la réglementation. Aujourd'hui, les facteurs économiques, la déréglementation des marchés, les progrès technologiques, le contrôle de l'Etat et, en général, les impératifs d'ouverture et de responsabilité, ont conduit les autorités de sûreté à réflechir à leur efficacité. De plus, les efforts pour relever le niveau actuel de sûreté sont perçus comme l'un des moyens de renforcer la confiance du public dans les systèmes de réglementation.
Ce rapport passe en revue les concepts de base de l'efficacité de l'autorité de sûreté, les progrès réalisés et les besoins futurs. Il s'adresse essentiellement aux autorités de sûreté nucléaire, mais pourrait également intéresser des représentants des instances gouvernementales, des exploitants de centrales nucléaires et le grand public.
Improving Nuclear Regulatory Effectiveness
English
, 48 pages, published: 05/03/01
NEA#3148
, ISBN: 92-64-18465-1
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3148-effectiveness.pdf
Other language(s):
- Francais:
Améliorer l'efficacité des autorités de sûreté nucléaire
Ensuring that nuclear installations are operated and maintained in such a way that their impact on public health and safety is as low as reasonably practicable has been and will continue to be the cornerstone of nuclear regulation. In the past, nuclear incidents provided the main impetus for regulatory change. Today, economic factors, deregulation, technological advancements, government oversight and the general requirements for openness and accountability are leading regulatory bodies to review their effectiveness. In addition, seeking to enhance the present level of nuclear safety by continuously improving the effectiveness of regulatory bodies is seen as one of the ways to strengthen public confidence in the regulatory systems.
This report covers the basic concepts underlying nuclear regulatory effectiveness, advances being made and future requirements. The intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested.
Assuring Future Nuclear Safety Competencies
Specific Actions
English
, 68 pages, published: 04/24/01
NEA#3146
, ISBN: 92-64-18462-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3146-competencies.pdf
In many countries, retiring nuclear safety experts are not being replaced by younger counterparts. This risks creating a shortfall in the number of experts available to ensure the effective regulation of the nuclear power industry. It could also result in the loss of much of the present nuclear safety knowledge base. This report discusses specific ways to maintain future nuclear safety competencies in nuclear regulatory authorities and the nuclear industry.
Nuclear Safety Research in OECD Countries
Summary Report of Major Facilities and Programmes at Risk
English
, 60 pages, published: 04/20/01
NEA#3144
, ISBN: 92-64-18463-5
Available online at:
http://www.oecd-nea.org/nsd/reports/nea3144-research.pdf
Major nuclear safety research facilities and programmes are facing increasing budgetary constraints, and in many cases are being closed or terminated. This report identifies major facilities of vital interest to the international nuclear safety community and makes recommendations for their continued operation in an international framework, either as joint projects or centres of excellence.
Nuclear Regulatory Challenges Arising from Competition in Electricity Markets
Bilingual
, 34 pages, published: 02/12/01
NEA#2948
, ISBN: 92-64-08460-6
Available online at:
http://www.oecd-nea.org/nsd/reports/nea2948-comp.pdf
In recent years a world-wide trend has been developing to introduce competition in electricity markets. As market competition unfolds, it produces a wide range of safety challenges for nuclear power plant operators and regulators.
Nuclear regulators must be aware of the potential safety challenges produced and consider whether new regulatory response strategies are warranted. This report describes many of these challenges, their implications and possible regulatory response strategies.
The intended audience is primarily nuclear safety regulators, although government authorities, nuclear power plant operators and the general public may also be interested.
On assiste depuis quelques années au développement de la concurrence dans les marchés de l'électricité à l'échelle mondiale. Au fur et à mesure que cette concurrence se développe, elle entraîne une grande variété de défis de sûreté pour les exploitants de centrales nucléaires et les autorités réglementaires.
Les autorités de sûreté doivent être conscientes des défis de sûreté potentiels et examiner le besoin éventuel de nouvelles stratégies de réponse réglementaire. Ce rapport décrit plusieurs de ces défis, leurs implications et les stratégies de réponse réglementaire éventuelle.
Le public vise est avant tout les autorités de sûreté nucléaire, mais les autorités gouvernementales, les exploitants de centrales nucléaires et le grand public pourront également être interessés.
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Regulatory Response Strategies for Safety Culture Problems
Bilingual
, 25 pages, published: 01/01/00
NEA#2248
, ISBN: 92-64-07672-7
Available online at:
http://www.oecd-nea.org/nsd/reports/nea2248-response.pdf
Since 1998 the NEA Committee on Nuclear Regulatory Activities (CNRA) has been dealing with the issue of how a regulatory organisation can recognise early, and address safety performance problems that stem from, safety culture weaknesses. Following a report published in 1999 entitled "the Role of the Nuclear Regulator in Promoting and Evaluating Safety Culture", this report explores regulatory response strategies for dealing with declining safety performance. It also discusses resumption of normal surveillance after a period of enhanced regulatory attention and intervention.The intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested.
Depuis 1998, le Comité de l'AEN sur les activités nucléaires réglementaires (CANR) s'intéresse à la manière dont une autorité de sûreté identifie et traite à un stade précoce les problèmes de sûreté provenant de lacunes dans la culture de sûreté. Faisant suite à un rapport publié en 1999 et intitulé "Le rôle de l'autorité de sûreté dans la promotion et l'évaluation de la culture de sûreté", le présent ouvrage explore des stratégies de réponse réglementaire à la baisse du niveau de sûreté. Il aborde également le retour à un mode de surveillance normal après une période de surveillance et d'intervention renforcée décidée par les autorités de sûreté. Ce rapport s'adresse en premier lieu aux autoirtés de sûreté nucléaire, mais pourra également présenter un intérêt pour les autorités gouvernementales, les exploitants nucléaires et le public.
Assuring Nuclear Safety Competence into the 21st Century
Workshop Proceedings, Budapest, Hungary, 12-14 October 1999
English
, 246 pages, published: 01/01/00
NEA#2528
, ISBN: 92-64-18517-8
Available online at:
http://www.oecd-nea.org/nsd/pubs/2000/2528-assuring-competence.pdf
Irrespective of current views on the future of nuclear power programmes, concerns are arising with respect to the long-term ability to preserve safety competence because student enrolments in nuclear engineering are decreasing rapidly and experienced staff are reaching retirement age. "Assuring Nuclear Safety Competence into the 21st Century" was discussed in depth by workshop participants. The need for a long-term strategic view was emphasised, and policy recommendations were made. Thes proceedings will be of particular interest to those playing a policy role in the nuclear industry, regulatory bodies and the education sector.
Nuclear Power Plant Operating Experiences from the IAEA/NEA Incident Reporting System
1996-1999
English
, 44 pages, published: 01/01/00
NEA#2288
, ISBN: 92-64-17671-3
Available online at:
http://www.oecd-nea.org/nsd/reports/nea2288-IRS.pdf
The Incident Reporting System (IRS) is an essential element of the international operating experience feedback system for nuclear power plants. IRS reports contain information on events of safety significance with important lessons learned. These experiences assist in reducing or eliminating recurrence of events at other plants. The IRS is jointly operated and managed by the Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA), a specialised agency within the United Nations system. This report highlights important lessons learned from events reported to the IRS over the period of July 1996-June 1999. A total of 342 events were reported by the participating countries during this time. Several areas were selected in this report to show the range of important topics available in the IRS. These include several different types of failure in a variety of systems, as well as experience of human errors in combination with system failures. It is important that sufficient national resources be allocated to enable timely reporting of events important to safety, and to share these events in the IRS database. This report is intended to provide general information for senior officials in industry and government who have decision-making roles in the nuclear power industry.
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Loss of Tendon Prestress in NPP Containments
Proceedings of a WANO/OECD Workshop, Poitiers, France, August 1997
NEA/CSNI/R(97)9
English
, 378 pages, published: 01/01/98
NEA#987
General Distribution Document Number: OCDE/GD(97)225
Available online at:
http://www.oecd-nea.org/nsd/docs/1997/csni-r1997-09.pdf
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Irradiation Embrittlement and Optimisation of Annealing
Proceedings of a Specialist meeting, Paris, France, 20-23 September 1993 - jointly organised by the OECD/NEA and the IAEA - NEA/CSNI/R(94)1
Principal Working Group No. 3 on Primary Circuit Integrity
English
, 547 pages, published: 01/01/97
NEA#325
General Distribution Document Number: OCDE/GD(97)23
Available online at:
http://www.oecd-nea.org/nsd/docs/1994/csni-r1994-1.pdf
Safety Research Needs for Russian-Designed Reactors
English
, 64 pages, published: 01/01/97
NEA#270
, ISBN: 92-64-15669-0
Available online at:
http://www.oecd-nea.org/nsd/pubs/1998/0270-safety-research-russian-reactors.pdf
Other language(s):
- Français:
Recherches sur la sûreté des réacteurs de conception russe - Etat des besoins
The OECD Nuclear Energy Agency co-operates with both the central and eastern European countries and the New Independent States of the former Soviet Union in planning and executing safety research programmes. The purpose is to build up know-how and capabilities in safety technology pertaining to their nuclear power plants. In this report, senior safety experts from Russia and Western countries review the nuclear-safety research needed to improve the safety of Russian-designed nuclear power reactors. They have selected a number of important research topics to which priority should be given. They have also identified nuclear-safety research topics that would benefit from a collaborative effort between eastern and western nuclear-safety researchers.
Recherches sur la sûreté des réacteurs de conception russe - Etat des besoins
Français
, 72 pages, published: 01/01/97
NEA#271
, ISBN: 92-64-25669-5
Available online at:
http://www.oecd-nea.org/nsd/pubs/1998/0271-recherche-sûreté.pdf
Other language(s):
- English:
Safety Research Needs for Russian-Designed Reactors
L'Agence de l'OCDE pour l'énergie nucléaire collabore avec les pays d'Europe centrale et orientale et les nouveaux Etats indépendants de l'ex-Union soviétique à la planification et l'exécution des programmes de recherche sur la sûreté qui permettront à ces pays d'acquérir le savoir-faire et les compétences spécifiques à leurs filières de centrales nucléaires. Dans ce rapport, d'éminents spécialistes de la sûreté russes et occidentaux dressent un bilan des recherches nécessaires pour améliorer la sûreté des réacteurs de conception russe. Sont répertoriés, d'une part, les sujets de recherche importants à traiter en priorité et, de l'autre, les domaines les plus susceptibles de bénéficier d'une collaboration entre l'Est et l'Ouest.
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