A Common Objective, a Variety of Paths Third International Conference on Geological Repositories, Berne, Switzerland, 15-17 October 2007 (2009)
A Common Objective, a Variety of Paths Synthesis and Main Lessons:Third International Conference on Geological Repositories, Berne, Switzerland, 15-17 October 2007 (2009)
Achieving the Goals of the Decommissioning Safety Case A Status Report (2005)
Applying Decommissioning Experience to the Design and Operation of New Nuclear Power Plants (2010)
Approaches and Challenges for the Use of Geological Information in the Safety Case for Deep Disposal of Radioactive Waste Third AMIGO Workshop Proceedings, Nancy, France, 15-17 April 2008 (2009)
Clay Club Catalogue of Characteristics of Argillaceous Rocks (2005)
Considering Timescales in the Post-closure Safety of Geological Disposal of Radioactive Waste (2009)
Cost Estimation for Decommissioning An International Overview of Cost Elements, Estimation Practices and Reporting Requirements (2010)
Cultural and Structural Changes in Radioactive Waste Management Organisations Lessons Learnt (2007)
Decommissioning Considerations for New Nuclear Power Plants (2010)
Decommissioning Funding: Ethics, Implementation, Uncertainties A Status Report (2006)
Decommissioning of Nuclear Facilities (brochure) It can and has been done (2009)
Disposal of Radioactive Waste: Forming a New Approach in Germany FSC Workshop Proceedings, Hitzacker and Hamburg, Germany, 5-8 October 2004 (2006)
Engineered Barrier Systems (EBS) in the Context of the Entire Safety Case Process Issues - Workshop Proceedings, Las Vegas, United States, 14-17 September 2004 (2005)
Engineered Barrier Systems (EBS) in the Safety Case: Design Confirmation and Demonstration Workshop Proceedings, Tokyo, Japan, 12-15 September 2006 (2007)
Engineered Barrier Systems (EBS) in the Safety Case: The Role of Modelling Workshop Proceedings, La Coruna, Spain, 24-26 August 2005 (2007)
Fostering a Durable Relationship Between a Waste Management Facility and its Host Community Adding Value Through Design and Process (2007)
Geological Repositories: Political and Technical Progress Workshop Proceedings, Stockholm, Sweden, 8-10 December 2003 (2005)
International Experiences in Safety Cases for Geological Repositories (INTESC) + CD-ROM Outcomes of the INTESC Project (2009)
International Peer Reviews for Radioactive Waste Management General Information and Guidelines (2005)
Linkage of Geoscientific Arguments and Evidence in Supporting the Safety Case Second AMIGO Workshop Proceedings, Toronto, Canada, 20-22 September 2005 (2007)
Management of Uncertainty in Safety Cases and the Role of Risk Workshop Proceedings, Stockholm, Sweden, 2-4 February 2004 (2005)
More than Just Concrete Realities: The Symbolic Dimension of Radioactive Waste Management (2010)
Moving Forward with Geological Disposal of Radioactive Waste A Collective Statement by the NEA Radioactive Waste Management Committee (RWMC) (2008)
NEA Sorption Project Phase II Interpretation and Prediction of Radionuclide Sorption onto Substrates Relevant for Radioactive Waste Disposal Using Thermodynamic Sorption Models (2005)
Natural Tracer Profiles Across Argillaceous Formations: The CLAYTRAC Project (2009)
Optimisation of Geological Disposal of Radioactive Waste National and International Guidance and Questions for Further Discussion (2010)
Partnering for Long-term Management of Radioactive Waste Evolution and Current Practice in Thirteen Countries (2010)
Radioactive Waste Management Programmes in OECD/NEA Member Countries (2005)
Radioactive Waste Management in Spain: Co-ordination and Projects FSC Workshop Proceedings, L'Hospitalet de l'Infant, Spain, 21-23 November 2005 (2007)
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together Synthesis of the FSC National Workshop and Community Visit, Bar-le-Duc, France, 7-9 April 2009 (2010)
Radioactivity Measurements at Regulatory Release Levels A Task Group Report (2006)
Regional Development and Community Support for Radioactive Waste Management (web only) Synthesis of the FSC National Workshop and Community Visit, Tengelic and Bataapati, Hungary, 14-17 November 2006 (2009)
Regulating the Decommissioning of Nuclear Facilities Relevant Issues and Emerging Practices (2008)
Regulating the Long-term Safety of Geological Disposal Towards a Common Understanding of the Main Objectives and Bases of Safety Criteria (2007)
Regulating the Long-term Safety of Geological Disposal of Radioactive Waste: Practical Issues and Challenges Workshop Proceedings, Paris, France, 28-30 November 2006 (2008)
Regulation and Guidance for the Geological Disposal of Radioactive Waste A Review of the Literature and Initiatives of the Past Decade (2010)
Release of Radioactive Materials and Buildings from Regulatory Control A Status Report (2008)
Releasing the Sites of Nuclear Installations A Status Report (2006)
Safety Cases for Deep Geological Disposal of Radioactive Waste: Where Do We Stand? Symposium Proceedings, Paris, France, 23-25 January 2007 (2008)
Safety of Geological Disposal of High-level and Long-lived Radioactive Waste in France An International Peer Review of the “Dossier 2005 Argile” Concerning Disposal in the Callovo-Oxfordian Formation (2006)
Selecting Strategies for the Decommissioning of Nuclear Facilities A Status Report (2006)
Self-sealing of Fractures in Argillaceous Formations in the Context of Geological Disposal of Radioactive Waste Review and Synthesis (2010)
Stability and Buffering Capacity of the Geosphere for Long-term Isolation of Radioactive Waste Application to Argillaceous Media - "Clay Club" Workshop Proceedings, Braunschweig, Germany, 9-11 December 2003 (2005)
Stability and Buffering Capacity of the Geosphere for Long-term Isolation of Radioactive Waste: Application to Crystalline Rock Workshop Proceedings, Manchester, United Kingdom, 13-15 November 2007 (2009)
Stakeholder Involvement in Decommissioning Nuclear Facilities International Lessons Learnt (2007)
The NEA Co-operative Programme on Decommissioning A Decade of Progress (2006)
The Regulatory Function and Radioactive Waste Management International Overview (2005)
The Roles of Storage in the Management of Long-lived Radioactive Waste Practices and Potentialities in OECD Countries (2006)
Towards Greater Harmonisation of Decommissioning Cost Estimates (2010)
Towards Transparent, Proportionate and Deliverable Regulation for Geological Disposal Workshop Proceedings, Tokyo, Japan, 20-22 January 2009 (2010)
Synopsis
International peer reviews as a working method is closely associated with OECD practice, where it is facilitated by the homogeneous membership and the high degree of trust shared by the member countries. International peer reviews of national radioactive waste management programmes, or of specific aspects of them, have been increasingly carried out over the past ten years. This document lays down the guidelines that the requesting country, the Secretariat and the international review team ought to have in mind when an international peer review is requested, organised or carried out.
La revue internationale par des pairs est un outil de travail étroitement lié aux pratiques de l'OCDE, dont l'emploi est facilité par l'homogénéité de ses pays membres et par la grande confiance qui règne entre eux. Des revues internationales par des pairs de programmes nationaux de gestion des déchets radioactifs, ou de certains de leurs aspects spécifiques, ont été réalisées de façon croissante depuis les dix dernières années. Ce document décrit les lignes directrices dont le pays demandeur, le Secrétariat et l'équipe internationale d'experts doivent tenir compte lorsqu'une revue internationale par des pairs est demandée, organisée ou réalisée.
Synopsis
Experience from decommissioning projects suggests that the decommissioning of nuclear power plants could be made easier if this aspect received greater consideration at the design stage and during operation of the plants. Better forward planning for decommissioning results in lower worker doses and reduced costs. When appropriate design measures are not taken at an early stage, their introduction later in the project becomes increasingly difficult. Hence, their early consideration may lead to smoother and more effective decommissioning operations. This report provides an overview of key decommissioning issues which are useful to consider when designing new nuclear power plants.
Synopsis
Disposal of high-level radioactive waste and spent nuclear fuel in engineered facilities, or repositories, located deep underground in suitable geological formations is being developed worldwide as the reference solution to protect humans and the environment both now and in the future. Assessing the long-term safety of geological disposal requires developing a comprehensive understanding of the geological environment. The transport pathways are key to this understanding. Of particular interest are fractures in the host rock, which may be either naturally occurring or induced, for example, during the construction of engineered portions of a repository. Such fractures could provide pathways for migration of contaminants.
In argillaceous (clay) formations, there is evidence that, over time, fractures can become less conductive and eventually hydraulically insignificant. This process is commonly termed “self-sealing”. The capacity for self-sealing relates directly to the function of clay host rocks as migration barriers and, consequently, to the safety of deep repositories in those geological settings.
This report – conducted under the auspices of the NEA Clay Club – reviews the evidence and mechanisms for self-sealing properties of clays and evaluates their relevance to geological disposal. Results from laboratory tests, field investigations and geological analogues are considered. The evidence shows that, for many types of argillaceous formations, the understanding of self-sealing has progressed to a level that could justify its inclusion in performance assessments for geological repositories.
Synopsis
This report is based on a study carried out by the NEA Decommissioning Cost Estimation Group (DCEG) on decommissioning cost elements, estimation practices and reporting requirements. Its findings indicate that cost methodologies need to be updated continuously using cost data from actual decommissioning projects and hence, systematic approaches need to be implemented to collect these data. The study also concludes that changes in project scope may have the greatest impact on project costs. Such changes must therefore be identified immediately and incorporated into the estimate. Finally, the report notes that more needs to be done to facilitate the comparison of estimates, for example by providing a reporting template for national estimates.
This publication is also available in French as: Intégration du retour d'expérience du démantèlement à la conception et l'exploitation des futures centrales nucléaires (WEB ONLY) -
Synopsis
Experience from decommissioning projects suggests that the decommissioning of nuclear power plants could be made easier if it received greater consideration at the design stage and during the operation of the plants. Better forward planning for decommissioning results in lower worker doses and reduced costs. When appropriate design measures are not taken at an early stage, their introduction later in the project becomes increasingly difficult. Hence, their early consideration may lead to smoother and more effective decommissioning.
It is now common practice to provide a preliminary decommissioning plan as part of the application for a licence to operate a nuclear facility. This means, in turn, that decommissioning issues are being considered during the design process. Although many design provisions aiming at improved operation and maintenance will be beneficial for decommissioning as well, designers also need to consider issues that are specific to decommissioning, such as developing sequential dismantling sequences and providing adequate egress routes. These issues and more are discussed in this report.
This publication is also available in French as: Au-delà des seules réalités concrètes : la dimension symbolique de la gestion des déchets radioactifs -
Synopsis
Key concepts of radioactive waste management, such as safety, risk, reversibility and retrievability, carry different meanings for the technical community and for non-technical stakeholders. Similarly, socio-economic concepts, including community, landscape and benefit packages, are interpreted differently by diverse societal groups. Opinions and attitudes are not simply a faithful reflection of decision making, actual events and communicated messages; perceptions and interpretations of events and objects also play a role. This report presents key issues and examples in order to build awareness of the importance of symbols and symbolism in communicating about perceptions and interpretations. It adds to the recognition that dialogue amongst stakeholders is shaped by dimensions of meaning that reach beyond dictionary definitions and are grounded in tradition and social conventions. A better understanding of these less obvious or conspicuous realities should help find additional ways of creating constructive relationships amongst stakeholders.
This publication is also available in French as: Stockage des déchets radioactifs et territoires d'accueil : envisager l'avenir ensemble - Synthèse de l'atelier du FSC et des rencontres avec les collectivités locales, Bar-le-Duc, France, 7-9 April 2009
Synopsis
This 7th Forum on Stakeholder Confidence (FSC) workshop focused on the territorial implementation of France’s high-level and long-lived intermediate-level waste management programme. Sessions addressed the French historical and legislative context, public information, reversibility, environmental monitoring and the issue of memory. Amongst the participants were representatives of local and regional governments, civil society organisations, universities, waste management agencies, institutional authorities and delegates from 13 countries. This report provides a synthesis of the workshop deliberations.
This publication is also available in French as: Partenariats pour la gestion à long terme des déchets radioactifs - Evolution et pratique actuelle dans treize pays
Synopsis
National radioactive waste management programmes are in various phases of siting facilities and rely on distinct technical approaches for different categories of waste. In all cases, it is necessary for institutional actors and the potential or actual host community to build a meaningful, workable relationship. Partnership approaches are effective in achieving a balance between the requirements of fair representation and competent participation. With host community support, they also help ensure the desirable combination of a licensable site and management concept as well as a balance between compensation, local control and development opportunities. This report provides up-to-date information on experience with local partnership arrangements in 13 countries. The characteristics, advantages and aims of community partnerships are also described in addition to the concept's evolution over the past decade.
This publication is also available in French as: Vers une harmonisation des estimations des coûts du déclassement -
Synopsis
Currently, the format, content and practice of cost estimation vary considerably both within and between countries, which makes it very difficult to compare estimates, even for similar types of facilities. The reasons are largely due to different legal requirements in different countries and to historical custom and practice, leading to variations in basic assumptions such as the anticipated decommissioning strategy and end state of the site, and to different approaches to dealing with uncertainties. While attaining harmonisation across national approaches to cost estimation may be difficult to achieve, standardising the way decommissioning cost estimates are structured and reported will give greater transparency to the decommissioning process and will help build regulator and stakeholder confidence in the cost estimates and schedules.
This booklet highlights the findings of the NEA Decommissioning Cost Estimation Group (DCEG) which recently studied cost estimation practices in 12 countries.
This publication is also available in French as: Optimisation des stockages géologiques de déchets radioactifs - Recommandations nationales et internationales et futurs thèmes de discussions
Synopsis
As national geological disposal programmes progress towards implementation, the concept of “optimisation” and related requirements are receiving increased attention. Exchanges within NEA expert groups have shown that both regulators and implementers would benefit from a review of the relevant concepts and available guidance and experience. This report summarises and reviews the concepts relevant to the “optimisation” of geological disposal systems as they are outlined in national and international guidance. It also presents a set of observations and key questions. Overall, the report shows that, when addressing “optimisation”, there is ample scope for clarifying concepts, facts and possibilities and for ensuring that regulatory guidance is sufficiently precise and implementable. The intention is that this report should serve as a basis for discussion within and beyond NEA committees and expert groups.
Synopsis
As part of its activities, the Regulators’ Forum of the NEA Radioactive Waste Management Committee has been examining the regulatory criteria for the long-term performance of geological disposal. In this context, it organised a workshop entitled “Towards Transparent, Proportionate and Deliverable Regulation for Geological Disposal”, which served to verify current status and needs. Participants included regulators, implementers, policy makers, R&D specialists and academics. Themes addressed included duties to future generations, timescales for regulation, stepwise decision making, roles of optimisation and best available techniques (BAT), multiple lines of reasoning, safety and performance indicators, recognition of uncertainties and the importance of stakeholder interactions. The workshop highlighted the significant amount of work accomplished over the past decade, but also identified important differences between national regulations even if these are not in contradiction with international guidance. Also highlighted was the importance of R&D carried out on behalf of the regulator. In addition to the contributed papers, these proceedings trace the numerous discussions that formed an integral part of the workshop. They constitute an important and unique documentary basis for researchers and radioactive waste management specialists.
This publication is also available in French as: Réglementation et lignes directrices pour l'évacuation des déchets radioactifs en formation géologique - Revue de la littérature et des initiatives de la dernière décennie
This publication is also available in French as: Expériences internationales des dossiers de sûreté pour les dépôts en formation géologique (INTESC) - Résultats du projet INTESC
Synopsis
A “safety case” is the synthesis of evidence, analyses and arguments that quantify and substantiate a claim that a geological repository for radioactive waste will be safe after closure and beyond the time when active control of the facility can be ensured. The NEA project on International Experiences in Safety Cases for Geological Repositories (INTESC) analysed existing safety cases, and their elements, to provide an overview of progress during the last decade, to identify key concepts and to give insight into regulatory expectations on the contents and review of safety cases. This report documents the outcomes of the INTESC project. It takes account of the responses to a detailed survey of NEA member countries as well as the results of a technical workshop.
The project has shown that the purpose and concept of a safety case are generally understood, accepted and adopted by radioactive waste management programmes worldwide. Programmes are preparing safety cases in line with most of the elements suggested by the NEA, although there are some differences in interpretation and presentation. Some important trends are emerging, such as the use of safety functions and the role of a geosynthesis. Further development of some aspects and tools, such as quality assurance programmes and requirements management systems, can be expected as safety cases are further refined to support programmes moving towards implementation of geological disposal.
This publication is also available in French as: Démantèlement d'installations nucléaires - C'est possible et cela a été fait
Synopsis
Considerable international experience gained over the last 20 years demonstrates that nuclear facilities can be safely dismantled and decommissioned once a decision is made to cease operations and permanently shut them down. This brochure looks at decommissioning across a spectrum of nuclear facilities and shows worldwide examples of sucessful projects.
Synopsis
High-level political, governmental and regulatory decision makers, as well as representatives of economic and social groups and implementing organisations met in Berne, Switzerland to present and to reflect on their collective experience towards meeting the challenge of implementing national disposal projects for placing radioactive waste in deep geological formations. This summary highlights the main lessons to be learnt and final recommendations to assist future developments in national radioactive waste management programmes seeking to meet both technical and social imperatives of modern society.
Synopsis
In November 2006, Hungary hosted the 6th National Workshop and Community Visit of the NEA Forum on Stakeholder Confidence (FSC). Participants included institutional authorities, local residents and stakeholders, 11 mayors and more than 30 FSC delegates from 12 countries. The workshop focused on those factors that contribute either to the success or failure of the siting process for a radioactive waste repository. Experience gained in Hungary over the past two decades provided the context for the discussions. The workshop highlighted the role and modes of operation of local public oversight and information associations, which proved to be instrumental in reaching an agreement between the implementer and the local communities. The workshop included a visit to the community of Bátaapáti and the ongoing project site for an underground repository for short-lived, low- and intermediate-level radioactive waste (LILW).
Synopsis
High-level political, governmental and regulatory decision makers, as well as representatives of economic and social groups and implementing organisations met in Berne, Switzerland to present and to reflect on their collective experience towards meeting the challenge of implementing national disposal projects for placing radioactive waste in deep geological formations. These proceedings include the papers presented at the conference as well as a summary which highlights the main lessons to be learnt and final recommendations to assist future developments in national radioactive waste management programmes seeking to meet both technical and social imperatives of modern society.
Synopsis
A cornerstone of national decision making and societal acceptance of deep geological disposal of radioactive waste is confidence that such repositories can protect humans and the environment both now and in the future. The “safety case” is the synthesis of evidence, analyses and arguments that quantify and substantiate a claim that the repository will be safe after closure and beyond the time when active control of the facility is ensured. For deep geological disposal, studies of the geosphere form a principal component of the safety case. Geoscientific information is unique in that it can offer evidence and lines of reasoning that span geological timescales (millennia and even longer).
The NEA Approaches and Methods for Integrating Geological Information in the Safety Case (AMIGO) project addresses the collection and integration of geoscientific evidence, analyses and arguments that contribute to an understanding of long-term safety. The third and final AMIGO workshop on “Approaches and Challenges for the Use of Geological Information in the Safety Case” underscored that geoscientific information plays a fundamental role in safety assessments. It is also increasingly used in the wider context of the safety case to provide evidence and arguments for the intrinsically favourable properties of a site, including its long-term stability. No single geoscientific argument “proves” safety, but rather each supports some key element of the safety case and provides enhanced confidence in the safety case. The workshop also considered the links and feedback among the safety case; design, engineering and construction issues; and geoscientific investigations.
Synopsis
Disposal of high-level radioactive waste and spent nuclear fuel in engineered facilities, or repositories, located deep underground in suitable geological formations is being developed worldwide as the reference solution to protect humans and the environment both now and in the future. An important aspect of assessing the long-term safety of deep geological disposal is developing a comprehensive understanding of the geological environment in order to define the initial conditions for the disposal system as well as to provide a sound scientific basis for projecting its future evolution. The transport pathways and mechanisms by which contaminants could migrate in the surrounding host rock are key elements in any safety case. Relevant experiments in laboratories or underground test facilities can provide important information, but the challenge remains in being able to extrapolate the results to the spatial and temporal scales required for performance assessment, which are typically tens to hundreds of metres and from thousands to beyond a million years into the future. Profiles of natural tracers dissolved in pore water of argillaceous rock formations can be considered as large-scale and long-term natural experiments which enable the transport properties to be characterised.
The CLAYTRAC Project on Natural Tracer Profiles Across Argillaceous Formations was established by the NEA Clay Club to evaluate the relevance of natural tracer data in understanding past geological evolution and in confirming dominant transport processes. Data were analysed for nine sites to support scientific understanding and development of geological disposal. The outcomes of the project show that, for the sites and clay-rich formations that were studied, there is strong evidence that solute transport is controlled mainly by diffusion. The results can improve site understanding and performance assessment in the context of deep geological disposal and have the potential to be applied to other sites and contexts.
Synopsis
Geological settings selected as potential host formations for the deep geological disposal of radioactive waste are chosen for, among other assets, their long-term stability and buffering capacity against disruptive or destabilising events and processes. The NEA Integration Group for the Safety Case organised a workshop on geosphere stability to develop a better understanding of the scientific evidence and arguments that contribute to confidence in the geological stability for deep geological disposal.
These proceedings present the outcomes of a geosphere stability workshop, held in November 2007, that focused on crystalline and other types of hard, fractured rocks. The workshop underscored the fact that many such rocks are intrinsically stable environments that evolve extremely slowly and provide good buffering against external events and processes. There is a good understanding of the processes and events that can affect crystalline rocks and, although there is less confidence in predicting exactly when and where such events will occur and the volume of rock that will be affected, the extent of the impacts on a geological repository can be confidently addressed using bounding approaches supported by geological information from similar sites around the world.
Synopsis
A key challenge in the development of safety cases for the deep geological disposal of radioactive waste is handling the long time frame over which the radioactive waste remains hazardous. The intrinsic hazard of the waste decreases with time, but some hazard remains for extremely long periods. Safety cases for geological disposal typically address performance and protection for thousands to millions of years into the future. Over such periods, a wide range of events and processes operating over many different timescales may impact on a repository and its environment. Uncertainties in the predictability of such factors increase with time, making it increasingly difficult to provide definite assurances of a repository's performance and the protection it may provide over longer timescales. Timescales, the level of protection and the assurance of safety are all linked.
Approaches to handling timescales for the geological disposal of radioactive waste are influenced by ethical principles, the evolution of the hazard over time, uncertainties in the evolution of the disposal system (and how these uncertainties themselves evolve) and the stability and predictability of the geological environment. Conversely, the approach to handling timescales can affect aspects of repository planning and implementation including regulatory requirements, siting decisions, repository design, the development and presentation of safety cases and the planning of pre- and post-closure institutional controls such as monitoring requirements. This is an area still under discussion among NEA member countries. This report reviews the current status and ongoing discussions of this issue.
This publication is also available in French as: Libération des matériaux et bâtiments radioactifs du contrôle réglementaire - Rapport de synthèse
Synopsis
The radiological concept of clearance can be defined as the release of radioactive materials or buildings from any further regulatory control applied for radiological protection purposes by the competent body. It is generally based on the assumption that, following clearance, any potential radiological exposure of the public will be trivial.
Clearance is now a mature concept being used for the management of large amounts of radioactive materials (including metals, building rubble, cables and plastics) and disused buildings associated with a controlled nuclear activity. There are, however, differences in the ways in which clearance is dealt with in the regulatory frameworks of various countries and the ways in which clearance has been implemented in diverse decommissioning projects.
This report provides up-to-date information on an array of national approaches to clearance. It should be of particular help to those planning the implementation of a clearance procedure, such as that for decommissioning a nuclear facility.
This publication is also available in French as: Dispositions réglementaires pour le déclassement des installations nucléaires - Points importants et pratiques émergentes
Synopsis
The removal of fuel from a permanently shutdown nuclear facility eliminates the major source of radiological hazard, a nuclear criticality. Combined with the cessation of operations at high temperatures and pressures, the risk to public health and to the environment is thereby very significantly reduced. The process of decommissioning does however necessitate processes involving both conventional and radiological hazards such as the cutting and dismantling of structures, plant and equipment and the use of explosive cutting techniques. Some radiological hazards remain because of the possibility of coming into contact with radioactively contaminated or activated material.
This report considers how regulatory arrangements are being adapted to the continuously changing environment, and associated risk levels in a nuclear facility that is being decommissioned. It uses examples of current practices in several countries with large decommissioning programmes to illustrate emerging regulatory trends.
This publication is also available in French as: Progresser sur la voie du stockage géologique des déchets radioactifs - Déclaration collective du Comité de la gestion des déchets radioactifs (RWMC) de l'AEN
Synopsis
The NEA Radioactive Waste Management Committee (RWMC) has underscored the environmental and ethical basis for geological disposal as well as its technical feasibility in a number of previous collective statements. In the intervening period there have been advances and evolving views regarding the appropriate methodologies, policies, and decision-making processes. In addition much further practical experience has accumulated regarding the development of geological repositories. The RWMC expresses herewith, in a concise form, its collective views on why geological disposal remains an appropriate waste management choice for the disposal of the most hazardous and long-lived radioactive wastes, on the current status of geological disposal, on challenges and opportunities for implementation, and expectations for further developments.
Synopsis
Regulating the long-term safety of geological disposal of radioactive waste is a key part of making progress on the radioactive waste management issue. A survey of member countries has shown that differences exist both in the protection criteria being applied and in the methods for demonstrating compliance, reflecting historical and cultural differences between countries which in turn result in a diversity of decision-making approaches and frameworks. At the same time, however, these differences in criteria are unlikely to result in significant differences in long-term protection, as all the standards being proposed are well below levels at which actual effects of radiological exposure can be observed and a range of complementary requirements is foreseen.
In order to enable experts from a wide range of backgrounds to debate the various aspects of these findings, the NEA organised an international workshop in November 2006 in Paris, France. Discussions focused on diversity in regulatory processes; the basis and tools for assuring long-term protection; ethical responsibilities of one generation to later generations and how these can be discharged; and adapting regulatory processes to the long time frames involved in implementing geological disposal. These proceedings include a summary of the viewpoints expressed as well as the 22 papers presented at the workshop.
Synopsis
The OECD Nuclear Energy Agency (NEA) hosted an international symposium on “Safety Cases for the Deep Disposal of Radioactive Waste: Where Do We Stand?” in January 2007. The NEA has spearheaded important developments in defining, and in developing methodologies to support, demonstrations of safety for deep disposal, including a similar symposium nearly two decades ago that provided the basis for a 1991 NEA collective opinion that the technical basis and methods exist for undertaking safety assessment of deep geological disposal. The 2007 symposium, co-sponsored by the European Commission and the International Atomic Energy Agency, provided the opportunity to review progress and to identify emerging trends and challenges. It brought together experts in the field of radioactive waste disposal from waste management organisations, regulatory agencies, scientific support organisations, international agencies, private sector consultants, and public interest groups both within and beyond NEA member countries.
The symposium showed that safety cases for radioactive waste disposal have evolved to become important tools both to assess safety and to aid in decision making. There is a good, shared understanding of what a safety case is and what comprises its main components. Importantly, the concept of a safety case today encompasses not only quantitative assessments of potential repository performance but also includes additional (and often more qualitative) lines of evidence and arguments that can contribute to confidence in safety. There has been significant evolution in terms of the analytical tools, lines of evidence, range of performance indicators and communication of the safety case. The value of international co-operation and dialogue in developing the concept and methodology of safety cases was underscored. These proceedings describe the discussions and conclusions of the symposium, and provide copies of the technical papers presented.
This publication is also available in French as: Réglementation de la sûreté à long terme du stockage géologique - Vers une compréhension commune des objectifs principaux et des fondements des critères de sûreté
Synopsis
Regulating the long-term safety of geological disposal of radioactive waste poses special challenges due to the very long timescales involved. This report has been prepared to help foster a common understanding of the fundamental safety objectives of deep geological repositories and the applicable criteria. It provides important guidance for the national programmes that are developing or refining regulations. A common understanding may also contribute to clearer communication and public understanding of regulatory criteria.
This publication is also available in French as: Changements culturels et organisationnels dans les organismes de gestion des déchets radioactifs - Enseignements tirés
Synopsis
In recent years the socio-political environment of radioactive waste management (RWM) has been changing in a significant way. Stakeholder dialogue has become a leading principle. How have RWM organisations adapted to this societal transition? How do they balance the requirement of openness and the increasing concerns over the security of facilities? Are there organisations that have successfully changed from a technical- to a customer-focused culture? What resistance was met? Which tools and instruments helped organisations evolve?
This report documents the changes observed by RWM managers and sets those changes in an organisational sciences framework. All those who are intent on learning about the changes that have taken place in the field of radioactive waste management, or whose own organisations in any sector must adapt to societal demand, will be interested by the experience and insight reported here.
Synopsis
The presence of several barriers serving complementary safety functions enhances confidence that radioactive waste placed in deep geological repositories will be adequately isolated and contained to protect human health and the environment. The barriers include the natural geological barrier and the engineered barrier system (EBS). The EBS itself may comprise a variety of sub-systems or components, such as the waste form, container, buffer, backfill, seals and plugs. Given the importance of this subject, the Integration Group for the Safety Case (IGSC) of the OECD Nuclear Energy Agency (NEA) sponsored a series of workshops with the European Commission to develop greater understanding of how to achieve the necessary integration for the successful design, testing, modelling and performance assessment of EBS for deep underground disposal of radioactive waste.
These proceedings present the main findings from, and the papers delivered at, the fourth NEA-EC workshop on EBS, which took place in Tokyo, Japan, in September 2006. This final workshop of the series focused on strategies and methods to demonstrate that EBS designs will fulfil the relevant requirements for long-term safety, engineering feasibility and quality assurance. The workshop highlighted that large-scale experiments have confirmed the feasibility of techniques for manufacturing and installing engineered components in disposal systems and have also provided valuable lessons to improve designs and refine practical aspects to construct and implement EBS.
Synopsis
The sixth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ENRESA, the Spanish agency responsible for the management of radioactive waste and the dismantling of nuclear power plants, and the Council of Nuclear Safety (CSN), with the support of the Association of Spanish Municipalities in Areas Surrounding Nuclear Power Plants (AMAC). The workshop took place at L'Hospitalet de l'Infant, Catalonia, Spain, on 21-23 November 2005.
At this workshop, Spanish stakeholders and delegates from 14 countries discussed current co-ordination of radioactive waste management decision making in Spain. Findings were shared from Cowam-Spain, a co-operative research project on the involvement of local stakeholders, the relationship between national and local levels of decision making, and the long-term sustainability of decisions regarding the siting of a centralised interim storage facility for high-level waste. These proceedings include the workshop presentations and discussions, as well as the rapporteurs' reflections on what was learned about policy making and participative decision making.
Synopsis
The long-term safety of deep disposal of radioactive waste will be strongly dependent on the performance of the geological setting. The geology fulfils important safety functions including isolating the waste from human contact or intrusion, providing a stable physical and chemical environment, insulating against external disturbances, and preventing or delaying the transport of radioactive materials away from the waste. Thus, a sound understanding of the geology's history and evolution is central in supporting assessments that examine the long-term performance and safety of deep disposal. Geological data can also play an important role in other related activities, such as site selection and repository design.
Through a series of technical workshops, the OECD Nuclear Energy Agency (NEA) project on Approaches and Methods for Integrating Geological Information in the Safety Case (AMIGO), is devoted to defining and improving the collection and use of geological evidence that contribute to the understanding of long-term safety for radioactive waste disposal. The second AMIGO workshop was organised in Canada in September 2005. It examined how geoscientific arguments and data are compiled and linked to create a unified description of the geological setting to support a safety case. It also examined practical aspects and limitations in collecting, linking, extrapolating and communicating such information. These proceedings present the outcomes of the workshop.
This publication is also available in French as: Implication des parties prenantes dans le déclassement des installations nucléaires - Enseignements internationaux
Synopsis
Significant numbers of nuclear facilities will need to be decommissioned in the coming decades. In this context, NEA member countries are placing increasing emphasis on the involvement of stakeholders in the associated decision procedures. This study reviews decommissioning experience with a view to identifying stakeholder concerns and best practice in addressing them. The lessons learnt about the end of the facility life cycle can also contribute to better foresight in siting and building new facilities. This report will be of interest to all major players in the field of decommissioning, in particular policy makers, implementers, regulators and representatives of local host communities.
This publication is also available in French as: Créer un lien durable entre une installation de gestion de déchets et sa collectivité d'accueil - Valeur ajoutée à travers la conception et les processus
Synopsis
Any long-term radioactive waste management project is likely to last decades to centuries. It requires a physical site and will impact in a variety of ways on the surrounding community over that whole period. The societal durability of an agreed solution is essential to success. This report identifies a number of design elements (including functional, cultural and physical features) that favour a durable relationship between the facility and its host community by improving prospects for quality of life across generations.
Synopsis
In the deep disposal of radioactive waste, the presence of several barriers serving complementary safety functions enhances confidence that the waste will be isolated and contained to protect human health and the environment. The barriers include the natural geological barrier and the engineered barrier system (EBS). The EBS itself may comprise a variety of sub-systems or components, such as the waste form, container, buffer, backfill, seals and plugs. The Integration Group for the Safety Case (IGSC) of the Nuclear Energy Agency (NEA) is co-sponsoring a series of workshops with the European Commission to develop greater understanding of how to achieve the necessary integration for the successful design, testing, modelling and performance assessment of engineered barrier systems (EBS) for deep underground disposal of radioactive waste.
These proceedings include the main findings and presented papers from the third NEA-EC workshop on engineered barrier systems, which focused on the role of EBS modelling in the safety case for deep disposal. Some national programmes are placing increased emphasis on EBS and, as implementation of underground repositories approaches, more realistic assessments of EBS performance are needed. The workshop examined the modelling tools currently available and identified complex areas of assessment in which further dialogue is needed.
Synopsis
The NEA Co-operative Programme for the Exchange of Scientific and Technical Information Concerning Nuclear Installation Decommissioning Projects (CPD) is a joint undertaking which functions within the framework of an agreement between 21 organisations actively executing or planning the decommissioning of nuclear facilities. The objective of the CPD is to acquire and share information from operational experience in the decommissioning of nuclear installations that is useful for future projects. The information exchange also ensures that best international practice is made widely available and encourages the application of safe, environmentally friendly and cost-effective methods in all decommissioning projects. By the end of 2006, the Programme scope included 26 reactors, 8 reprocessing plants and 8 fuel facility projects.
This report describes the progress made and the main results obtained by the CPD during 1995-2005. Although part of the information exchanged within the CPD is confidential and restricted to programme participants, experience of general interest gained under the programme’s auspices is released for broader use. Such information is brought to the attention of all NEA members through regular reports to the NEA Radioactive Waste Management Committee (RWMC), as well as through experience summary documents such as this report. The RWMC Working Party on Decommissioning and Dismantling (WPDD) is grateful to the CPD for sharing the experience from its important work.
Synopsis
The release of radioactive materials from regulatory control is subject to release limits which are often based on published recommendations of international organisations, which aim to minimise radiological risks. The application of the recommendations has thus led to limits being set at very low activity levels. Adequate methods of measurement must be available to demonstrate or verify that the activity levels are lower than the recommended values. Measurements would also have to be made under practical industrial conditions, where various constraints could significantly influence the results. Hence, the costs of activity measurements at extremely low levels on large quantities of equipment with complex geometries could be prohibitively high.
The NEA Co-operative Programme on Decommissioning (CPD) established a special Task Group to study these issues in an analytical and structured manner. This report describes the group’s findings regarding the objectives and methodology for radiological characterisation and the equipment used for measurements. The report also contains case studies from NEA member countries and a critical discussion of different methods and techniques.
This publication is also available in French as: Les rôles de l'entreposage dans la gestion des déchets radioactifs à vie longue - Pratiques et potentialités dans les pays de l'OCDE
Synopsis
This report examines the roles that storage plays, or might play, in radioactive waste management in OECD/NEA member countries. A better understanding of these roles provides valuable input to current debates on the end-points of long-lived radioactive waste management. The report focuses on spent nuclear fuel, high-level waste from reprocessing and other long-lived, solid radioactive wastes.
This publication is also available in French as: Financement du démantèlementt : éthique, mise en œuvre, incertitudes - Rapport de synthèse
Synopsis
This status report on Decommissioning Funding: Ethics, Implementation, Uncertainties is based on a review of recent literature and materials presented at NEA meetings in 2003 and 2004, and particularly at a topical session organised in November 2004 on funding issues associated with the decommissioning of nuclear power facilities. The report also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD).
This report offers, in a concise form, an overview of relevant considerations on decommissioning funding mechanisms with regard to ethics, implementation and uncertainties. Underlying ethical principles found in international agreements are identified, and factors influencing the accumulation and management of funds for decommissioning nuclear facilities are discussed together with the main sources of uncertainties of funding systems.
This publication is also available in French as: Choisir des stratégies de démantèlement des installations nucléaires - Rapport de synthèse
Synopsis
This status report on Selecting Strategies for the Decommissioning of Nuclear Facilities is based on the viewpoints and materials presented at a seminar held in Tarragona, Spain on 1-4 September 2003 as well as the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). It identifies, reviews and analyses factors influencing decommissioning strategies and addresses the challenges associated with balancing these factors in the process of strategy selection. It gives recognition to the fact that, in addition to technical characteristics, there are many other factors that influence the selection of a decommissioning strategy and that cannot be quantified, such as policy, regulatory and socio-economic factors and aspects that reach far into the future. Uncertainties associated with such factors are a challenge to those who have to take decisions on a decommissioning strategy.
Potentially interested groups of readers are regulators, implementers, R&D experts and policy makers dealing with decommissioning and dismantling issues as well as politicians, decision makers and the general public.
This publication is also available in French as: Libération des sites des installatons nucléaires - Rapport de synthèse
Synopsis
Releasing the site of a nuclear installation from radiological control is usually one of the last steps of decommissioning. To date, site release has been practised in a limited number of cases only as most decommissioning projects have not yet advanced to a state where the release of the site is imminent or because the site will continue to be used for nuclear activities. Therefore, for a number of decommissioning projects where planning for site release will soon start, this status report provides useful considerations based on NEA member country experience and expert advice.
In addition to describing the basic considerations which must be taken into account when deciding on the release of a site, the status report provides guidance on establishing release criteria. The report also addresses site release implementation, measurement techniques and underground contamination. It will be of particular interest to regulators, implementers, R&D experts and policy makers dealing with decommissioning and dismantling issues.
This publication is also available in French as: Sûreté du stockage géologique de déchets radioactifs HAVL en France - Examen international par des pairs du "Dossier 2005 Argile" concernant le stockage dans la formation du Callovo-Oxfordien
Synopsis
A major activity of the OECD Nuclear Energy Agency (NEA) in the field of radioactive waste management is the organisation of international peer reviews of national studies and projects. The peer reviews help national programmes assess accomplished work. The general comments expressed in the reviews are also of potential interest to other member countries. The present review was carried out to inform the French Government whether the "Dossier 2005 Argile" prepared by the National Agency for the Management of Radioactive Waste (Andra) was consistent with international practices and whether future research needs were properly identified.
Synopsis
Germany is exploring a new approach towards the final management of its radioactive waste. This international workshop, held in Germany, attracted 65 participants from 13 countries. A little more than half of the participants were German stakeholders.
During the workshop invited speakers, representing different groups of stakeholders, commented on relevant aspects of the new German approach being proposed. This served as a basis for subsequent round-table discussions.
These proceedings provide a historical introduction to radioactive waste management in Germany, give a detailed summary of the workshop presentations and discussions that took place, and also provide the NEA Secretariat's reflections which help place the main lessons of the workshop into a wider perspective. Five presentations - the three keynote papers and the two thematic reports - are also reproduced herein.
This publication is also available in French as: Vers la réalisation d'un dossier de sûreté de démantèlement - Rapport de synthèse
Synopsis
The key issue in the decommissioning of nuclear facilities is the progressive removal of hazards, by stepwise decontamination and dismantling activities that have to be carried out safely and within the boundaries of an approved safety case. The decommissioning safety case is a collection of arguments and evidence to demonstrate the safety of a decommissioning project. The safety case involves analysing the hazards and the separate stages required for hazard reduction. This status report, drawn from the activities of the OECD/NEA Working Party on Decommissioning and Dismantling (WPDD), will be helpful to individuals and organisations involved in the preparation of a decommissioning safety case.
This publication is also available in French as: La fonction réglementaire et la gestion des déchets radioactifs - Panorama international
Synopsis
This overview presents an easily accessible synopsis of the regulatory control of radioactive waste management in 15 NEA member countries. It covers the management of radioactive waste from all types of nuclear installations, such as nuclear power plants, research reactors and nuclear fuel cycle facilities. It also addresses medical, research and industrial sources as well as defence-related sources where relevant. The overview should be of interest to a wide audience of both specialists and non-specialists.
This publication is also available in French as: Programmes de gestion des déchets radioactifs dans les pays membres de l'OCDE/AEN -
Synopsis
These fact sheets present the radioactive waste management programmes of 20 OECD/NEA member countries. They include information about the sources, types and quantities of waste as well as how and by whom they are managed. References for further information are also provided for each country.
Synopsis
The integration Group for the Safety Case (IGSC) of the Nuclear Energy Agency (NEA) is co-sponsoring a project with the European Commission to develop a greater understanding of how to achieve the necessary integration for successful design, construction, testing, modelling an performance assessment of engineered barrier systems (EBS). These proceedings include the main findings and presented papers from the second workshop of the EC-NEA EBS project, which covered inter alia research and development work on pre- and post-closure processes; thermal management; thermal, hydraulic, mechanical and chemical process models; and repository design. The workshop was hosted by the US Department of Energy in Las Vegas, USA, on 14-17 September 2004.
Synopsis
The OECD/NEA Working Group on the Characterisation, the Understanding and the Performance of Argillaceous Rocks as Repository Host Formations, namely the "Clay Club", examines the various argillaceous rocks that are being considered for the deep geological disposal of radioactive waste, i.e. from plastic, soft, poorly indurated clays to brittle, hard mudstones or shales. The Clay Club considered it necessary and timely to provide a catalogue to gather in a structured way the key geoscientific characteristics of the various argillaceous formations that are - or were - studied in NEA member countries with regard to radioactive waste disposal. The present catalogue represents the outcomes of this Clay Club initiative.
Synopsis
The modelling of the key process of radionuclide sorption is of great importance in assessing the performance or safety of deep and near-surface repositories for radioactive waste. The first phase of the NEA Sorption Project ran from 1997 to 1998, and highlighted the diversity in the details of the thermodynamic descriptions of sorption processes. Phase II of the NEA Sorption Project was initiated as a major international contribution towards demonstrating the consistency and applicability of different thermodynamic sorption models to support the selection of a sorption parameter, namely Kd values for safety assessments. It was implemented in the form of a comparative modelling exercise based on selected datasets for radionuclide sorption by both simple and complex materials.
This report presents the results of Phase II of the Sorption Project, conducted as a co-operative project under the auspices of the Integration Group for the Safety Case (IGSC) of the OECD/NEA Radioactive Waste Management Committee (RWMC).
Synopsis
Most experts worldwide agree that radioactive waste disposal in engineered facilities, or repositories, located in appropriate formations deep underground, provide a suitable waste management option for protecting humans and the environment now and in the future.
An NEA workshop was organised on 9-11 December 2003 in Braunschweig, Germany, devoted specifically to argillaceous settings for deep geological repositories. The workshop brought together scientists from academic institutions, engineers from various research institutions or companies, consultants, regulatory authorities and national waste management organisations to establish the scientific basis for stability and buffering capacity of deep geological waste management systems. The present report synthesises the main outcomes of that workshop and presents a compilation of the related abstracts.
Synopsis
The OECD Nuclear Energy Agency (NEA) organised a workshop on the "Management of Uncertainty in Safety Cases and the Role of Risk" in Stockholm, Sweden, on 2-4 February 2004. The workshop's main objective was to discuss different approaches to treating uncertainties in safety cases for radioactive waste management facilities, and more specifically how concepts of risk can be used in both post-closure safety cases and regulatory evaluations.This report includes a synthesis of the plenary presentations and the discussions that took place during the workshop. These proceedings will be of interest to waste repository safety assessors and managers.
Synopsis
Various long-term radioactive waste management options have been considered in order to protect humans and the environment both now and in the future. Most experts worldwide agree that disposal in engineered facilities, or repositories, located in appropriate formations deep underground, provides a suitable option. Engineered geological disposal is seen as a radioactive waste management end-point providing security and safety in a sustainable manner that does not necessarily require monitoring, maintenance and institutional control. Internationally, this option is regarded to be technically feasible, acceptable from an ethical and environmental viewpoint, as well as acceptable from an international legal perspective.
The Stockholm International Conference on Geological Repositories: Political and Technical Progress brought together over 200 high-level decision makers and other interested stakeholders from the national, regional and local levels. Regulatory bodies and radioactive waste management implementing organisations also took part. In addition to providing a forum for the exchange of the most up-to-date information in the field, it also served to strengthen international co-operation on radioactive waste management and disposal issues.
This publication is also available in English as: Decommissioning of Nuclear Facilities (Update 2005 brochure) - It can and has been done
This publication is also available in English as: Applying Decommissioning Experience to the Design and Operation of New Nuclear Power Plants -
Synopsis
L’expérience des projets de démantèlement de centrales nucléaires laisse entendre que l'on pourrait simplifier ces opérations si l'on y accordait davantage d'attention au moment de la conception ou pendant l'exploitation de l'installation. Mieux planifier le démantèlement est en effet synonyme de doses réduites et de moindres coûts. Or les adaptations de la conception qui n'ont pas été effectuées dès l'origine sont difficiles à introduire ultérieurement. C'est pourquoi, leur prise en compte précoce est gage d'un démantèlement plus facile et plus efficace.
Il est dorénavant de pratique courante de produire un plan de démantèlement préliminaire avec la demande d'autorisation d’exploitation d'une centrale nucléaire. Cela signifie que les questions de démantèlement sont prises en compte pendant la conception. Toutefois, si les dispositions de conception adoptées pour l’exploitation et la maintenance améliorent souvent les conditions de démantèlement aussi, les concepteurs doivent également considérer les aspects spécifiques à ces opérations, établir des séquences d'opérations de démantèlement et prévoir des voies d'évacuation adaptées par exemple. Ce rapport approfondit ces questions et bien d'autres encore.
This publication is also available in English as: More than Just Concrete Realities: The Symbolic Dimension of Radioactive Waste Management -
Synopsis
Les concepts clés de la gestion des déchets radioactifs, tels la sûreté, le risque, la réversibilité et la récupérabilité, ont des connotations différentes pour la communauté scientifique et pour les parties prenantes de formation non technique. De manière similaire, des concepts socio-économiques, dont la communauté, le paysage et les avantages sociaux, sont interprétés différemment suivant les groupes sociaux. Les opinions et les comportements ne sont pas simplement une image fidèle de la prise de décision, des événements réels et des messages communiqués ; la perception et l’interprétation des événements et des objets jouent aussi un rôle. Ce rapport présente les questions clés et des exemples permettant de développer la prise de conscience de l’importance des symboles et du symbolisme dans la communication sur les perceptions et les interprétations. Il accentue le constat que la communication entre les parties prenantes est modelée par des dimensions qui vont au-delà du sens commun et sont fondées sur les traditions et les conventions sociales. Une meilleure compréhension de ces réalités moins évidentes ou flagrantes devrait aider à trouver des moyens additionnels pour créer des relations constructives entre les parties prenantes.
This publication is also available in English as: Radioactive Waste Repositories and Host Regions: Envisaging the Future Together - Synthesis of the FSC National Workshop and Community Visit, Bar-le-Duc, France, 7-9 April 2009
Synopsis
La thématique de ce 7e atelier du Forum sur la confiance des parties prenantes (FSC) concernait la mise en œuvre du programme français de gestion des déchets de haute activité et de moyenne activité à vie longue. Au cours des différentes sessions, ont été abordés le contexte historique et législatif français, l’information du public, la réversibilité, la surveillance de l’environnement ainsi que la conservation de la mémoire. Des représentants des collectivités locales et régionales, des représentants d’organisations de la société civile, des universités, des agences de gestion des déchets et des délégués de 13 pays y ont participé. Ce rapport présente une synthèse des délibérations de l’atelier.
This publication is also available in English as: Partnering for Long-term Management of Radioactive Waste - Evolution and Current Practice in Thirteen Countries
Synopsis
Les programmes nationaux de gestion des déchets radioactifs se trouvent à des phases diverses dans la recherche de sites d’implantation d’installations et se fondent sur des approches techniques distinctes adaptées aux différentes catégories de déchets. Dans tous les cas, il est nécessaire que les acteurs institutionnels et la communauté d’accueil, actuelle ou potentielle, établissent entre eux une relation sérieuse et viable. Les formules de partenariat permettent de réaliser un équilibre entre les exigences d’une représentation équitable et d’une participation éclairée. Avec l'appui de la communauté d’accueil, elles contribuent également à l'association souhaitable d’un site et d’un concept de gestion pouvant être autorisés au plan réglementaire ainsi qu'à un bon équilibre entre l'octroi de compensations, le contrôle local et les possibilités de développement. Ce rapport présente les informations les plus récentes sur les expériences de partenariat avec les communautés d’accueil dans 13 pays. Les caractéristiques, les avantages et les objectifs de telles formules de partenariat y sont décrits ainsi que l'évolution du concept sur les dix dernières années.
This publication is also available in English as: Towards Greater Harmonisation of Decommissioning Cost Estimates -
Synopsis
À l'heure actuelle, on observe une variabilité considérable dans le format, le contenu et les pratiques d'estimation des coûts, que ce soit à l'intérieur d'un même pays ou lorsque l'on franchit les frontières. Les comparaisons sont, de ce fait, extrêmement difficiles, même entre installations du même type. Les exigences de la réglementation sont principalement responsables de ces disparités, ainsi que les habitudes et pratiques historiques. Elles se répercutent sur les hypothèses de base, telles que la stratégie de démantèlement prévue et l'état final du site, mais aussi sur les méthodes de traitement des aléas. Il sera sans doute difficile d'harmoniser les approches nationales des estimations des coûts. On peut du moins recommander une structure et une présentation standard de nature à accentuer la confiance que l'autorité de contrôle et les parties prenantes pourront accorder aux estimations et aux calendriers de dépenses.
Cette brochure présente les conclusions du groupe d’estimation des coûts du démantèlement (DCEG), qui a récemment étudié la façon dont étaient estimés les coûts dans 12 pays.
This publication is also available in English as: Optimisation of Geological Disposal of Radioactive Waste - National and International Guidance and Questions for Further Discussion
Synopsis
Alors que les programmes nationaux de stockage géologique progressent vers leur mise en œuvre, le concept d’« optimisation » et les exigences réglementaires associées suscitent une attention accrue. Les échanges au sein des groupes d’experts de l’AEN ont montré que les régulateurs et les maîtres d’ouvrage pourraient ensemble tirer bénéfice d'un examen des concepts applicables ainsi que des recommandations et de l'expérience disponibles. Ce rapport récapitule et examine les concepts qui concernent l’« optimisation » des systèmes de stockage géologique tels qu'ils sont mis en avant dans les textes réglementaires nationaux et les recommandations internationales. Il présente également un certain nombre d'observations et de questions clés. De façon générale, il montre que, lorsque l’on traite de l’optimisation, il existe des marges substantielles pour clarifier les concepts, les faits et les options ainsi que pour s’assurer que les textes réglementaires sont suffisamment précis et applicables. L'objectif de ce rapport est de servir de base de discussions parmi et au delà des comités et des groupes d’experts de l’AEN.
This publication is also available in English as: Regulation and Guidance for the Geological Disposal of Radioactive Waste - A Review of the Literature and Initiatives over the Past decade
Synopsis
Un « dossier de sûreté » est la synthèse des preuves, analyses et arguments qui permettent de quantifier et de justifier que le dépôt de déchets radioactifs en formation géologique restera sûr après sa fermeture et après que l'on puisse assurer une surveillance active de l'installation. Le projet de l'AEN sur les International Experiences in Safety Cases for Geological Repositories (INTESC) a consisté à analyser les dossiers de sûreté actuels et leurs éléments afin de dresser un bilan des avancées des dix dernières années, d'en dégager les principaux concepts et de préciser les attentes futures des autorités de sûreté concernant le contenu et l'examen des dossiers de sûreté. Ce rapport présente les résultats du projet INTESC. Il tient compte des réponses à une enquête détaillée réalisée auprès des pays membres de l'AEN et intègre les résultats d'un atelier technique.
Le projet a montré que la finalité et le concept même du dossier de sûreté sont généralement bien compris, acceptés et adoptés par les gestionnaires de déchets à travers le monde. Les dossiers de sûreté préparés reprennent la plupart des éléments proposés par l’AEN, même s’il existe quelques différences d’interprétation et de présentation. Des tendances importantes se dessinent comme l'utilisation des fonctions de sûreté et le rôle de la synthèse des connaissances géologiques. À mesure que les dossiers de sûreté seront affinés pour permettre aux programmes d’avancer vers l’étape de la mise en œuvre du dépôt, on pourra également s’attendre à de nouveaux progrès dans l'analyse de certains aspects et l'élaboration d'outils, tels que les programmes d'assurance de la qualité et les systèmes de gestion des spécifications.
This publication is also available in English as: Release of Radioactive Materials and Buildings from Regulatory Control - A Status Report
Synopsis
En radioprotection, on entend par « libération » la décision prise par l'autorité compétente de lever tous les contrôles réglementaires appliqués jusqu'alors aux matériaux et bâtiments radioactifs. Cette décision se fonde généralement sur l'hypothèse que, si la décision de libération a été prise, alors toute dose d'exposition éventuelle ne sera que négligeable.
Ce concept de libération, aujourd'hui bien rodé, est utilisé pour gérer des matériaux radioactifs en grandes quantités (métaux, gravats, câbles, matières plastiques, etc.) mais aussi des bâtiments désaffectés qui étaient le siège d'une activité nucléaire contrôlée. On note toutefois des différences dans la manière de traiter la question de la libération dans la réglementation des différents pays ainsi que dans la mise en œuvre du concept suivant les projets de démantèlement.
Ce rapport propose aux lecteurs les dernières informations disponibles sur les différentes approches nationales de la libération. Il est destiné plus particulièrement à tous ceux qui s'apprêtent à entreprendre une procédure de libération, par exemple pour le démantèlement d'une installation nucléaire.
This publication is also available in English as: Regulating the Decommissioning of Nuclear Facilities - Relevant Issues and Emerging Practices
Synopsis
L’enlèvement des matières irradiées et plus particulièrement du combustible à l'issue de l'arrêt définitif d'une installation élimine la source principale de risque radiologique, le risque de criticité. Associé à l'arrêt de l'exploitation et à l'utilisation de procédés à haute température et pression, il induit une diminution significative des risques à la santé publique et à l'environnement. Les procédés utilisés lors des opérations de démantèlement – pour la découpe et le démontage de structures – induisent à la fois des risques conventionnels et radiologiques, comme par exemple les découpes à l'explosif. Des risques radiologiques demeurent en raison de la possibilité d'entrer en contact avec des matériels contaminés ou activés.
Ce rapport présente la nécessaire adaptation des contraintes réglementaires et aux risques associés liés aux opérations de démantèlement. Il présente des exemples de pratiques mises en œuvre dans plusieurs pays qui mènent de grands programmes de déclassement pour illustrer les nouvelles tendances réglementaires.
This publication is also available in English as: Moving Forward with Geological Disposal of Radioactive Waste - A Collective Statement by the NEA Radioactive Waste Managemen Committee (RWMC)
Synopsis
Le Comité de la gestion des déchets radioactifs (RWMC) de l’AEN a mis en avant les fondements environnementaux et éthiques relatifs au stockage géologique et s’est prononcé sur sa faisabilité technique par l’intermédiaire de plusieurs déclarations collectives antérieures. Depuis leur publication, aucun élément nouveau n'est venu remettre en cause leurs principales conclusions. Cependant, s’agissant des méthodologies, stratégies et processus de décision sur le sujet, des progrès ont été accomplis et les points de vue ont évolué. Le RWMC exprime ci-après, de manière concise, son opinion collective sur les raisons pour lesquelles le stockage géologique demeure une solution appropriée pour la gestion des déchets les plus dangereux et à vie longue. Il précise également l’état d’avancement des réflexions sur le stockage géologique, les défis et avantages de sa mise en œuvre ainsi que les attentes concernant les futurs développements.
This publication is also available in English as: Regulating the Long-term Safety of Geological Disposal - Towards a Common Understanding of the Main Objectives and Bases of Safety Criteria
Synopsis
La réglementation de la sûreté à long terme du stockage géologique des déchets radioactifs pose des défis particuliers en raison des vastes échelles de temps concernées. Ce rapport a été préparé afin de promouvoir une compréhension commune des objectifs fondamentaux et des critères de sûreté des dépôts en formation géologique profonde. Il indique des orientations importantes pour les programmes nationaux dont le développement ou le perfectionnement de la réglementation est en cours. Une compréhension commune pourrait aussi aider à une communication plus claire et à une meilleure compréhension des critères réglementaires par le public.
This publication is also available in English as: Cultural and Structural Changes in Radioactive Waste Management Organisations - Lessons Learnt
Synopsis
L'environnement sociopolitique de la gestion des déchets radioactifs a connu de profonds changements ces dernières années. La concertation avec les parties prenantes est devenue l’un des principes directeurs. Comment se sont adaptés les organismes gestionnaires des déchets à cette nouvelle donne ? Comment trouver l'équilibre entre la nécessité de transparence et la préoccupation croissante de sauvegarder la sécurité des installations ? Trouve-t-on des organismes qui ont réussi la transition d’une culture technocentriste à une culture axée sur le client ? Quelle opposition a été rencontrée ? Quels outils et instruments ont aidé les organismes à évoluer?
Ce rapport documente les changements observés par les gestionnaires de ce secteur, et place ces changements dans un cadre d'analyse provenant des sciences de l'organisation. L'expérience et les analyses rapportées seront d’intérêt pour tous ceux qui cherchent à savoir plus sur les changements opérés dans le domaine de la gestion des déchets radioactifs, ou dont la propre organisation – tous secteurs confondus – est appelée à s'adapter à la nouvelle donne sociale.
This publication is also available in English as: Decommissioning Funding: Ethics, Implementation, Uncertainties - A Statuts Report
Synopsis
Ce rapport de synthèse sur le Financement du démantèlement : éthique, mise en œuvre, incertitudes a été rédigé en s’appuyant sur la littérature récente et sur les informations présentées lors des réunions de l’AEN en 2003 et en 2004, notamment lors de la session thématique organisée en novembre 2004 sur le financement du démantèlement d’installations nucléaires. Ce rapport tire aussi parti de l’expérience du Groupe de travail de l’AEN sur le déclassement et le démantèlement (WPDD).
Sous une forme concise, il passe en revue les considérations que les mécanismes de financement du démantèlement suscitent en matière d’éthique, de mise en œuvre et d’incertitudes. Il présente les principes éthiques de base contenus dans les accords internationaux, décrit les facteurs influant sur la constitution et la gestion de fonds destinés au démantèlement d’installations nucléaires et expose les principales sources d’incertitudes des systèmes de financement.
This publication is also available in English as: Fostering a Durable Relationship Between a Waste Management Facility and its Host Community - Adding Value Through Design and Process
Synopsis
Tout projet de gestion de déchets radioactifs à long terme durera vraisemblablement des décennies, voire des siècles. Il nécessitera un site et influera de bien de manières sur la communauté environnante pendant toute cette période. L’adoption d’une solution durable d’un commun accord est essentielle à sa réussite. Le présent rapport identifie plusieurs éléments de conception (notamment des caractéristiques d’ordre fonctionnel, culturel et physique) pouvant favoriser l’instauration d’un lien durable entre l’installation et sa collectivité d’accueil, grâce à l’amélioration de ses perspectives de qualité de vie sur plusieurs générations.
This publication is also available in English as: Stakeholder Involvement in Decommissioning Nuclear Facilities - International Lessons Learnt
Synopsis
Un nombre significatif d’installations nucléaires devra être démantelé dans les prochaines décennies. Dans ce contexte, les pays membres de l’AEN accordent de plus en plus d’importance à l’implication des parties prenantes dans les processus de prise de décision. Cette étude passe en revue l'expérience acquise afin d’identifier d’une part les questions que les parties prenantes posent et d’autre part les meilleures approches pour y répondre. Les enseignements sur la fin du cycle de vie de ces installations peuvent aussi contribuer à mieux prévoir la localisation et la construction d’installations nouvelles. Ce rapport intéressera tous les acteurs principaux dans le domaine du déclassement, et notamment les politiques, les exploitants, les régulateurs et les représentants des communautés locales.
This publication is also available in English as: Selecting Strategies for the Decommissioning of Nuclear Facilities - A Status Report
Synopsis
Ce rapport de synthèse sur la façon de Choisir des stratégies de démantèlement des installations nucléaires repose sur les points de vue et les informations présentés au cours d'un séminaire organisé à Tarragone, en Espagne, du 1er au 4 septembre 2003 ainsi que sur l'expérience du Groupe de travail de l'AEN sur le déclassement et le démantèlement (WPDD). Il met en évidence, passe en revue et analyse les facteurs qui gouvernent les stratégies de démantèlement et se penche sur les problèmes soulevés par la recherche d'un compromis entre ces différents facteurs lors du choix d'une stratégie. Il prend en considération le fait que, parallèlement aux caractéristiques techniques, de nombreux autres facteurs qui ne peuvent être quantifiés influent sur le choix des stratégies de démantèlement : politiques, aspects réglementaires et socioéconomiques et divers autres facteurs ayant une portée dans un avenir éloigné. Les incertitudes associées à ces facteurs constituent un véritable défi pour ceux qui ont à prendre des décisions sur la stratégie de démantèlement.
Ce rapport sera susceptible d'intéresser les autorités de sûreté, les gestionnaires de déchets, les experts de R-D et les décideurs politiques confrontés à des problèmes de déclassement et de démantèlement ainsi que les politiciens, les décideurs et le grand public dans son ensemble.
This publication is also available in English as: Releasing the Sites of Nuclear Installations - A Status Report
Synopsis
La libération des sites d'installations nucléaires des contrôles radiologiques est généralement l'une des dernières étapes du déclassement. À ce jour, seul un petit nombre de projets en ont fait l'objet car la plupart des projets ne sont pas à la veille d'une libération ou continueront d'être utilisés pour des activités nucléaires. Par conséquent, pour les projets de déclassement sur le point de planifier la libération de sites, ce rapport de synthèse fournit des informations utiles, fruit de l'expérience des pays membres de l'AEN et des avis des spécialistes.
Outre sa description des aspects fondamentaux à prendre en compte lors de la décision de libérer un site, ce rapport de synthèse contient des conseils relatifs à la définition des critères de libération. Le rapport aborde également les questions liées à la libération des sites dans la pratique, les techniques de mesure et la contamination souterraine. Il sera d'un intérêt particulier pour les autorités de sûreté, les gestionnaires de déchets, les chercheurs et les décideurs traitant des questions de déclassement et de démantèlement.
This publication is also available in English as: Safety of Geological Disposal of High-level and Long-lived Radioactive Waste In France - An International Peer Review of the "Dossier 2005 Argile" Concerning Disposal in the Callovo-Oxfordian Formation
Synopsis
L'une des principales activités de l'Agence de l'OCDE pour l'énergie nucléaire (AEN) dans le domaine de la gestion des déchets radioactifs est d'organiser des examens internationaux d'études et de projets nationaux. Les examens aident les programmes nationaux à évaluer des travaux réalisés. Les observations d'ordre général faites dans les rapports des examens peuvent également présenter un intérêt pour d'autres pays membres. Cet examen a été mené afin d'informer le gouvernement français si le "Dossier 2005 Argile" élaboré par l'Agence nationale pour la gestion des déchets radioactifs (Andra) est en accord avec les pratiques internationales et si les futurs besoins en terme de recherche sont bien identifiés.
This publication is also available in English as: Learning and Adapting to Societal Requirements for Long-term Radioactive Waste Management - Key Findings and Experience of the Forum on Stakeholder Confidence
Synopsis
Ce rapport présente une synthèse des enseignements tirés par le Forum de l'AEN sur la confiance des parties prenantes (FSC) concernant la gouvernance de la gestion à long terme des déchets radioactifs. La plupart des conclusions s'appliquent à tout processus public d'élaboration de politiques, et ne se limitent pas à la gestion des déchets radioactifs. En se sens, ce rapport peut servir d'initiation aux problèmes concrets de gouvernance que pose toute décision complexe impliquant la collectivité.
This publication is also available in English as: Achieving the Goals of the Decommissioning Safety Case - A Status Report
Synopsis
Le problème clé dans le démantèlement des installations nucléaires est l'élimination progressive des risques, au moyen d'une série d'actions de décontamination et de déconstruction qui doivent être réalisées de façon sûre et dans les limites d'un dossier de sûreté approuvé. Le dossier de sûreté est une collection d'arguments et de documentation qui sert à démontrer la sûreté d'un projet de démantèlement. Le dossier de sûreté implique l'analyse des risques et des différentes phases nécessaires pour réduire les risques. Ce rapport de synthèse, qui s'appuie sur les activités du Groupe de travail de l'OCDE/AEN sur le déclassement et le démantèlement (WPDD), sera utile à toute personne et organisme engagés dans la préparation d'un dossier de sûreté de démantèlement.
This publication is also available in English as: The Regulatory Function and Radioactive Waste Management - International Overview
Synopsis
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.
This publication is also available in English as: Radioactive Waste Management Programmes in NEA Member Countries -
Synopsis
Ces fiches présentent les programmes de gestion des déchets radioactifs de 20 des pays membres de l'OCDE/AEN. Elles compilent des informations sur les sources, les sortes et les quantités de déchets aussi bien que comment et par qui ils sont gérés. Le lecteur y trouvera également les coordonnées des organismes concernés par la gestion des déchets dans chaque pays.
This publication is also available in English as: Stakeholder Involvement Techniques - A Short Guide and Annotated Bibliography
Synopsis
L'implication des parties prenantes, notamment par le dialogue et la délibération, peut améliorer la qualité et la durabilité des décisions prises par les pouvoirs publics. Cette publication offre au lecteur un guide concis aux techniques visant à s'assurer la participation des parties prenantes ainsi que les critères de sélection y afférents. Elle comporte aussi une bibliographie annotée indiquant les ouvrages et les autres ressources que l'on peut facilement se procurer sur le sujet. Bien que cette publication aborde la question sous l'angle de la gestion des déchets radioactifs, elle s'adresse aussi à toute personne ou organisation qui envisage une participation des parties prenantes dans le processus décisionnel.
This publication is also available in English as: Decommissioning of Nuclear Power Facilities - It can and has been done
Synopsis
Une des préoccupations majeures exprimée dans la production d'éléctricité d'origine nucléaire est que le démantèlement (déconstruction à un niveau donné) d'installations en fine de vie représente un problème majeur. L'expérience internationale démontre que cela n'est pas le cas. Cette brochure présente le démantèlement de la diversité des installations nucléaires au travers de projets mondiaux menés avec succès.
This publication is also available in English as: Stepwise Approach to Decision Making for Long-term Radioactive Waste Management - Experience, Issues and Guding Principles
Synopsis
Le processus de décision mis en place pour convevoir et mettre en oeuvre des modes de stockage à long terme des déchets radioactifs se déroule sur des décennies, comporte maintes étapes et fait intervenir une multitude d'acteurs. La clef de sa durabilité et de son succès est une grande flexibilité dans la conception et la conduite du processus. Des concepts tels que la "décision par étapes" et une "démarche itérative" offrent des moyens d'associer le public, en particulier les collectivités locales, à l'examen et à la planification des solutions envisagées pour le stockage des déchets radioactifs.
Cette étude de la décision par étapes dans la gestion à long terme des déchets radioactifs fait le point sur la situation, met en exergue la dimension sociale du processus et relève différents aspects de son application intéressant le spécialiste en sciences sociales et le spécialiste des déchets, constatant d'ailleurs une certaine convergence entre ces deux points de vue. Elle propose des principes généraux et objectifs d'action comme point de départ pour approfondir et améliorer ce concept.