Recent Publications

  A Common Objective, a Variety of Paths Synthesis and Main Lessons:Third International Conference on Geological Repositories, Berne, Switzerland, 15-17 October 2007 (2009)

  A Common Objective, a Variety of Paths Third International Conference on Geological Repositories, Berne, Switzerland, 15-17 October 2007 (2009)

  Actinide and Fission Product Partitioning and Transmutation + CD-ROM Tenth Information Exchange Meeting, Mito, Japan, 6-10 October 2008 (2010)

  Annual Report 2008 (2009)

  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)

  CSNI Technical Opinion Papers - No. 10 The Role of Human and Organisational Factors in Nuclear Power Plant Modifications (2009)

  CSNI Technical Opinion Papers - No. 11 Better Nuclear Plant Maintenance: Improving Human and Organisational Performance (2009)

  CSNI Technical Opinion Papers - No. 12 Research on Human Factors in New Nuclear Plant Technology (2009)

  Chemical Thermodynamics of Thorium - Volume 11 (2009)

  Considering Timescales in the Post-closure Safety of Geological Disposal of Radioactive Waste (2009)

  Decommissioning of Nuclear Facilities (brochure) It can and has been done (2009)

  Environmental Radiological Protection in the Law (Japanese version) - 法令にみる環境放射線防護 (2009)

  Evaluated Data Library for the Bulk of Fission Products (Volume 23) International Evaluation Co-operation, Volume 23 (2009)

  Evolution of the System of Radiological Protection Discussion of New ICRP Recommendations, 4th Asian Regional Conference, Tokyo, Japan, 13-14 December 2007 (2009)

  Experimental Facilities for Gas-cooled Reactor Safety Studies Task Group on Advanced Reactor Experimental Facilities (TAREF) (2009)

  Improving Nuclear Regulation Compilation of Regulatory NEA Guidance Booklets (2009)

  Independent Evaluation of the MYRRHA Project Report by an International Team of Experts (2009)

  Inter-code Comparison Exercise for Criticality Excursion Analysis Benchmarks Phase I: Pulse Mode Experiments with Uranyl Nitrate Solution Using the TRACY and SILENE Experimental Facilities (2009)

  International Experiences in Safety Cases for Geological Repositories (INTESC) + CD-ROM Outcomes of the INTESC Project (2009)

  Mixed-oxide (MOX) Fuel Performance Benchmark (PRIMO) Summary of the Results for the PRIMO BD8 MOX Rod (2009)

  Mobile Fission and Activation Products in Nuclear Waste Disposal Workshop Proceedings, La Baule, France, 16-19 January 2007 (2009)

  NEA News 27.2 (December 2009) (2009)

  Natural Tracer Profiles Across Argillaceous Formations: The CLAYTRAC Project (2009)

  Nuclear Energy Data 2009/Données sur l'énergie nucléaire 2009 (2009)

  Nuclear Energy and Addressing Climate Change (2009)

  Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions State-of-the-art Report (2009)

  Nuclear Fuel Cycle Synergies and Regional Scenarios for Europe (2009)

  Nuclear Fuel Cycle Transition Scenario Studies Status Report (2009)

  Nuclear Law Bulletin No. 83 (June 2009) (2009)

  Nuclear Law Bulletin No. 84 (December 2009) Volume 2009/2 (2009)

  Occupational Exposures at Nuclear Power Plants (2007) Seventeenth Annual Report of the ISOE Programme, 2007 (2009)

  PENELOPE-2008: A Code System for Monte Carlo Simulation of Electron and Photon Transport Workshop Proceedings, Barcelona, Spain, 30 June-3 July 2008 (2009)

  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)

  Research and Test Facilities Required in Nuclear Science and Technology (2009)

  Scientific Issues and Emerging Challenges for Radiological Protection (Japanese version) - 放射線防護における科学的問題と新たな課題 Report of the Expert Group on the Implications of Radiological Protection Science (2009)

  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)

  Strategic and Policy Issues Raised by the Transition from Thermal to Fast Nuclear Systems (2009)

  Summary Report of the CRPPH 50th Anniversary Conference Committee on Radiation Protection and Public Health (CRPPH), 31 May 2007 (2009)

  The Financing of Nuclear Power Plants (2009)

  The JEFF-3.1.1 Nuclear Data Library JEFF Report 22 - Validation Results from JEF-2.2 to JEFF-3.1.1 (2009)

  The JEFF-3.1/-3.1.1 Radioactive Decay Data and Fission Yields Sub-libraries JEFF Report 20 (2009)

  The NEA Contribution to the Evolution of the International System of Radiological Protection (2009)

  Work Management to Optimise Occupational Radiological Protection at Nuclear Power Plants (2009)

Detailed publications list by year

Synopsis

This new edition of Nuclear Energy Data, the OECD Nuclear Energy Agency’s annual compilation of essential statistics on nuclear energy in OECD countries, provides information on plans for new nuclear construction, nuclear fuel cycle developments and projections of installed nuclear capacity to 2035 in OECD member countries. This comprehensive overview of the current situation and expected trends in various sectors of the nuclear fuel cycle provides authoritative information for policy makers, experts and academics working in the nuclear energy field.

Cette nouvelle édition des Données sur l'énergie nucléaire de l'Agence de l'OCDE pour l’énergie nucléaire, une compilation annuelle de statistiques essentielles sur l'énergie nucléaire, décrit les projets de construction de centrales nucléaires et les développements dans le cycle du combustible et présente des projections de la puissance nucléaire installée dans les pays membres de l'OCDE jusqu'en 2035. Ce panorama complet de la situation actuelle et des tendances qui se dessinent dans divers secteurs du cycle du combustible nucléaire constitue l'ouvrage de référence pour les décideurs, les spécialistes et les chercheurs qui travaillent dans ce domaine.

This publication is also available in French as: Bulletin de droit nucléaire n° 84 (Décembre 2009) - Volume 2009/2

Synopsis

Considered to be the standard reference work for both professionals and academics in the field of nuclear law, the Nuclear Law Bulletin is a unique international publication providing its subscribers with up-to-date information on all major developments falling within the domain of nuclear law. Published twice a year in both English and French, it covers legislative developments in almost 60 countries around the world as well as reporting on relevant jurisprudence and administrative decisions, international agreements and regulatory activities of international organisations.

Feature articles in this issue include “Nuclear New Build – New Nuclear Law?”, “Directive Establishing a Community Framework for the Nuclear Safety of Nuclear Installations” and the “Harmonisation of Nuclear Liability in the European Union”.

Synopsis

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.

This publication is also available in French as: AEN Infos 27.2. (Décembre 2009) -

Synopsis

The renewed interest in nuclear energy – to a large extent stimulated by concerns about global climate change, high volatility of fossil fuel prices and security of energy supply – has also revived discussions on advanced reactor concepts with the potential to reduce significantly the long-term radioactivity of nuclear waste. One of these concepts is an accelerator-driven system (ADS) which combines a particle accelerator with a subcritical reactor core. The Belgian research centre SCK•CEN at Mol has launched a project aiming to construct an ADS consisting of a high energy proton, linear accelerator combined with a lead-bismuth-cooled, subcritical reactor. The project is called MYRRHA (Multi-purpose Hybrid Research Reactor for High-tech Applications).

The Belgian government asked the OECD Nuclear Energy Agency (NEA) to organise an international peer review of the MYRRHA project to provide an independent evaluation as part of the decision-making process. This report presents the findings from the review, which was conducted by a team of seven high-level experts from seven countries, assisted by the NEA Secretariat.

This publication is also available in as: Avis techniques du CSIN - n° 12 - Recherches sur le facteur humain dans les nouvelles centrales nucléaires

Synopsis

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.

This publication is also available in French as: Le financement des centrales nucléaires -

Synopsis

Many countries have recognised that greater use of nuclear power could play a valuable role in reducing carbon dioxide emissions. However, given the high capital cost and complexity of nuclear power plants, financing their construction often remains a challenge. This is especially true where such financing is left to the private sector in the context of competitive electricity markets.

This study examines the financial risks involved in investing in a new nuclear power plant, how these can be mitigated, and how projects can be structured so that residual risks are taken by those best able to manage them. Given that expansion of nuclear power programmes will require strong and sustained government support, the study highlights the role of governments in facilitating and encouraging investment in new nuclear generating capacity.

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.

Synopsis

放射線防護における科学的問題と新たな課題

科学的知見は、更に進化したテクノロジーが利用可能になるよう常に発展しており、より綿密な研究が実施されている。政策を決定し得る新たな研究成果である将来的な意味合い内容が提示され、1998年、NEAの放射線防護公共保健委員会（CRPPH）では放射線防護科学分野において最先端の研究調査を実施した。この調査は、放射線防護の現システムが科学的理解に支えられていることを示唆しており、様々な分野における知見の増大は、政策、規制に多大なインパクトを与える。10年後においても、CRPPHは再度、最先端の研究調査を繰り返し行い続け、先の結論を明確にする。

このレポートは放射線防護科学の最新のCRPPHアセスメントの結論を要約している。特に、個別機微な、標的とされていない知見、遅れた影響が、過去10年間に多大な改善をされ続けてきたことを説明している。それらは、まだこれらの分野である種非科学的であるにも関わらず、多くの最近の研究や調査を基に、レポートでは政策決定者や規制権者はこれから数年の研究から得られるであろう可能なインパクトを考えるべきだと堅調に示している。更に、レポートは政策選択においてより直接的インパクトを持つ科学的疑問に対し、より決定的な回答をするためにサポートされるべき研究分野を扱っている。

This publication is also available in French as: Le Démantèlement d'installations nucléaires - On peut le faire

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

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

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).

This publication is also available in French as: Besoins d'installations de recherche et d'expérimentation en sciences et technologies nucléaires -

Synopsis

Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy.

An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production.

This report contains the expert group’s detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities.

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

The Joint Evaluated Fission and Fusion (JEFF) Project is a collaborative effort among NEA Data Bank member countries to develop a reference nuclear data library for use in different energy applications. Radioactive decay data forms an integral part of the nuclear data requirements for nuclear applications. In 2005, a completely revised library, JEFF-3.1, was made available. The updated JEFF-3.1.1 Radioactive Decay Data and Fission Yields Sub-libraries were released in 2007.

This report describes the development, contents and initial validation of the JEFF-3.1 Radioactive Decay Data and Fission Yields Sub-libraries, including the 2007 update, JEFF-3.1.1, of these sub-libraries.

Synopsis

Regional strategies can provide a useful framework for implementing innovative nuclear fuel cycles. The appropriate sharing of efforts and facilities among different countries is necessary in today’s context, as is taking into account proliferation concerns and resource optimisation. The preliminary studies examined in this report show that the expected benefits deriving from partitioning and transmutation (P&T), notably the reduction of radiotoxicity and heat load in a shared repository, can bring advantages to all countries of the region concerned, even when different nuclear energy policies are pursued. The studies also demonstrate that regional strategies tend to favour a nuclear “renaissance” in some countries.

A regional approach is proposed in order to implement the innovative fuel cycles associated with partitioning and transmutation in Europe. The impact of different deployment strategies and policies in various countries is addressed. Regional facilities’ characteristics and potential deployment schedules are also discussed. Further studies should be undertaken to investigate practical issues (fuel transport in particular) and institutional issues which will, without doubt, be very challenging.

Synopsis

This publication reports the conclusions from the work undertaken by Subgroup 23 of the NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC), whose mission was to produce an international library of neutron cross-section evaluations for the most important fission products.

These fission products are important in the operation of nuclear reactors because some of them contribute delayed neutrons that are useful for reactor control, whereas others have a very high neutron capture cross-section, thus inhibiting the nuclear reaction. The build-up of the fission product poisons determines the maximum duration a given fuel element can be kept in a reactor.

Synopsis

法令にみる環境放射線防護

この出版物は国際、ヨーロッパ、そして国内の環境放射線防護に関する法律に係る調査について記述している。これにはオーストラリア、カナダ、フランス、日本、英国、そしてアメリカ合衆国の国々が網羅される。この法律に関する調査は、より良い環境を放射線からどのように保護できるかに触れており、現在のアプローチの強弱と併せ、規制における動向をどのように定義付けるかを扱っている。この本は、放射線防護分野の規制者、政策決定者だけでなく、環境規制に関心のある、より一般的な方への有用なものとなるであろう。

Synopsis

The evolution of the system of radiological protection is of great interest to governments and regulatory authorities, in particular in Asia. In this context, the Japanese government hosted a series of NEA conferences on this subject. The 4th Asian Regional Conference, held in Tokyo in December 2007, included key discussions of Japanese, Korean, Chinese and Russian views on the new International Commission on Radiological Protection (ICRP) recommendations, and on their interpretation in the international Basic Safety Standards and national regulations. This report summarises the most significant aspects of these discussions, providing keen insight into governmental and regulatory approaches to radiological protection in Asia.

This publication is also available in French as: Bulletin de droit nucléaire n° 83 (Juin 2009) -

Synopsis

Considered to be the standard reference work for both professionals and academics in the field of nuclear law, the Nuclear Law Bulletin is a unique international publication providing its subscribers with up-to-date information on all major developments falling within the domain of nuclear law. Published twice a year in both English and French, it covers legislative developments in almost 60 countries around the world as well as reporting on relevant jurisprudence and administrative decisions, international agreements and regulatory activities of international organisations.

Feature articles in this issue address “The Review Conference Mechanism in Nuclear Law: Issues and Opportunities”, “National Implementation and Enforcement of Nuclear-Weapon-Free Zone Treaties” and “The Decommissioning of Asse II – Burden of the Past in the Federal Republic of Germany".

Synopsis

The NEA Working Party on Nuclear Criticality Safety established an Expert Group on Criticality Excursion Analysis in 2001 to explore the performance of various transient codes to evaluate criticality accidents in a fissile solution. Inter-code comparison exercises among four transient codes (AGNES, CRITEX, INCTAC and TRACE) have been carried out with typical transient experiments using uranyl nitrate fuel solution.

Two sets of benchmarks were carried out based on experimental programmes performed in the TRACY reactor in Japan, and the SILENE reactor in France. TRACY and SILENE have the same geometrical features: an annular cylinder with a central void tube for a transient rod and similar operational modes for reactivity insertion. The experiments selected are representative benchmarks for low- and high-enriched uranyl nitrate solution, about 10 wt% for TRACY and 93 wt% for the SILENE core.

This report provides an analysis of the benchmark results obtained with four different codes. It will be of particular interest to criticality safety practitioners developing transient codes, notably since little experimental data is available and the existing transient codes are presently unavailable to the public.

This publication is also available in French as: La gestion du travail pour optimiser la radioprotection professionnelle dans les centrales nucléaires -

Synopsis

Since 1992, the Information System on Occupational Exposure (ISOE) has provided a forum for radiological protection professionals from nuclear power utilities and national regulatory authorities worldwide to discuss, promote and co-ordinate international co-operative undertakings for the radiological protection of workers at nuclear power plants. The ISOE objective is to improve occupational exposure management at nuclear power plants by exchanging relevant information, data and experience on methods to optimise occupational radiological protection.

This report on work management provides practical guidance on the application of work management principles as a contribution to the optimisation of occupational radiological protection. It recognises that while work management is no longer a new concept, continued efforts are needed to ensure that good performance, outcomes and trends are maintained in the face of current and future challenges. The focus of this report is therefore on presenting the key aspects of work management that should be considered by management and workers to save time, doses and money, supported by updated practical examples from within the ISOE community.

ISOE is jointly sponsored by the OECD Nuclear Energy Agency and the International Atomic Energy Agency (IAEA).

ISOE Network: www.isoe-network.net

Synopsis

The plutonium produced during the operation of commercial nuclear power plants or that has become available from the dismantlement of nuclear weapons needs to be properly managed. One important contribution to the management process consists in validating the calculation methods and nuclear data used for estimates concerning power systems burning mixed-oxide (MOX) fuel. Another important contribution is the improved modelling of MOX fuel behaviour in such systems.

Within the framework of the NEA Expert Group on Reactor-based Plutonium Disposition, a fuel modelling code benchmark test was carried out for MOX fuel, with irradiation data on the BD8 MOX rod of the PRIMO programme provided by SCK•CEN and Belgonucléaire. This report summarises the data provided and the fuel characteristics for the irradiation, and presents the calculation results provided by the contributors.

Synopsis

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.

Synopsis

Most experts worldwide agree that disposal of spent nuclear fuel in appropriate formations deep underground provides a suitable option. Most public discussions about these underground repositories concentrate on the radiological hazard associated with the potential leak of actinides to the biosphere. However, the radiotoxicity of the fission products dominates the total radiotoxicity of the spent nuclear fuel during the first 100 years. Thereafter, their radiotoxicity diminishes and the long-term radiotoxicity becomes dominated by the actinides, mainly by the plutonium and americium isotopes.

The aim of the international workshop on Mobile Fission and Activation Products in Nuclear Waste Disposal, MOFAP07, was to review and to identify the needs for further studies on the transport and chemical behaviour of fission products in the geosphere for the safety assessment of radioactive waste repositories. These proceedings contain 22 peer-reviewed papers from the workshop, which should be of particular interest to professionals in the radioactive waste management field.

Synopsis

The JEFF-3.1.1 library is an updated version of the JEFF-3.1 Joint Evaluated File for Fission and Fusion. It consists of sets of evaluated nuclear data for reactor applications. Reliable data of this sort are necessary to improve the safety and economy of existing installations, as well as for the design and efficient operation of advanced nuclear reactors. The improvements in this latest version of the JEFF-3.1.1 library are particularly noteworthy as regards light water reactor applications and the associated fuel cycle.

The present report provides detailed information on the analysis and incremental validation process employed with regard to the JEF-2.2 library, which has provided the basis for the JEFF-3.1.1 library.

This publication is also available in French as: Rapport annuel 2008 -

Synopsis

The Information System on Occupational Exposure (ISOE) was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. ISOE provides experts in occupational radiological protection with a forum for communication and exchange of experience.

The programme includes 71 participating utilities in 29 countries (334 operating units and 45 shutdown units), as well as the regulatory authorities of 25 countries. The ISOE database, annual symposia and ISOE Network website facilitate the exchange of operational experience and lessons learnt among participants.

The Seventeenth Annual Report of the ISOE Programme summarises occupational exposure data trends and ISOE achievements made during 2007. Principal developments in ISOE participating countries are also described.

ISOE is jointly sponsored by the OECD Nuclear Energy Agency and the International Atomic Energy Agency (IAEA).

ISOE Network: www.isoe-network.net

Synopsis

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.

This publication is also available in French as: Rapport de synthèse sur la conférence du 50e anniversaire du CRPPH - Comité de protection radiologique et de santé publique (CRPPH), 31 mai 2007

Synopsis

The NEA Committee on Radiation Protection and Public Health (CRPPH) celebrated its 50th anniversary in May 2007. Taking advantage of its half century of experience, the Committee took this occasion to look forward towards the next 50 years in order to identify the most significant emerging challenges to radiological protection policy, regulation and application. This report summarises the presentations and discussions of the high-level regulators and international radiological protection organisations’ leaders who attended, providing their views on how the radiological protection community can best move forward together to address emerging challenges.

This publication is also available in French as: La contribution de l'AEN à l'évolution du système international de protection radiologique -

Synopsis

Since the International Commission on Radiological Protection (ICRP) initiated a dialogue in 1999 on the evolution of the system of radiological protection, the NEA Committee on Radiation Protection and Public Health (CRPPH) has actively engaged in providing the ICRP with input and views. The Committee’s work on this subject has included eight expert group reports, seven international conferences, and four detailed review and comment assessments of draft ICRP recommendations. This report presents a chronological summary of the issues, views and concerns raised by the CRPPH as the ICRP issued various draft versions of its new recommendations (ICRP Publication 103, published in December 2007), and of the response by the ICRP as seen in its subsequent draft recommendations. The interest of this summary report is that it will not only assist readers in understanding the main themes and concepts of the new ICRP recommendations, but also why and how the changes from the previous ICRP Publication 60 recommendations came about.

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.

This publication is also available in French as: Questions stratégiques et politiques liées à la transition des systèmes nucléaires thermiques aux systèmes rapides -

Synopsis

The renewed interest in nuclear energy triggered by concerns about global climate change and security of supply, which could lead to substantial growth in nuclear electricity generation, enhances the attractiveness of fast neutron reactors with closed fuel cycles. Moving from the current fleet of thermal neutron reactors to fast neutron systems will require many decades and extensive RD&D efforts. This book identifies and analyses key strategic and policy issues raised by such a transition, aiming at providing guidance to decision makers on the best approaches for implementing transition scenarios.

The topics covered in this book will be of interest to government and nuclear industry policy makers as well as to specialists working on nuclear energy system analyses and advanced fuel cycle issues.

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: Avis techniques du CSIN - No. 11 - Améliorer la maintenance des centrales nucléaires en optimisant les performances humaines et organisationnelles

Synopsis

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.

Synopsis

Radiation is used in many applications of modern technology. However, its proper handling requires competent knowledge of the basic physical laws governing its interaction with matter. To ensure its safe use, appropriate tools for predicting radiation fields and doses, and subsequently establishing pertinent regulations, are required.

One area of radiation physics that has received much attention concerns electron-photon transport in matter. PENELOPE is a modern, general-purpose Monte Carlo tool for simulating the transport of electrons and photons, which is applicable for arbitrary materials and in a wide energy range. PENELOPE provides quantitative guidance for many practical situations and techniques, including electron and X-ray spectroscopies, electron microscopy and microanalysis, biophysics, dosimetry, medical diagnostics and radiotherapy, and radiation damage and shielding.

These proceedings contain the extensively revised teaching notes of the latest workshop/training course on PENELOPE (version 2008), along with a detailed description of the improved physics models, numerical algorithms and structure of the code system.

This publication is also available in French as: Avis techniques du CSIN - n° 10 - Le rôle des facteurs humains et organisationnels dans les modifications des centrales nucléaires

Synopsis

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.

Synopsis

Future nuclear fuel cycles could effectively address radioactive waste issues with the implementation of partitioning and transmutation (P&T). Previous studies have defined the infrastructure requirements for several key technical approaches. While these studies have proven extremely valuable, several countries have also recognised the complex, dynamic nature of the infrastructure problem: severe new issues arise when attempting to transit from current open or partially closed cycles to a final equilibrium or burn-down mode. While the issues are country-specific when addressed in detail, it is believed that there exists a series of generic issues related only to the current situation and to the desired end point.

These issues are critical to implementing a sustainable nuclear energy infrastructure. The present report focuses on the definition of key issues, the assessment of technologies and national scenario assessments.

Synopsis

This volume is the eleventh in the OECD Nuclear Energy Agency (NEA) “Chemical Thermodynamics” series. It is based on a critical review of the thermodynamic properties of thorium, its solid compounds and aqueous complexes, initiated as part of the NEA Thermochemical Database Project Phase III (TDB III). The database system developed at the OECD/NEA Data Bank ensures consistency not only within the recommended data sets of thorium, but also amongst all the data sets published in the series. This volume will be of particular interest to scientists carrying out performance assessments of deep geological disposal sites for radioactive waste.

This publication is also available in English as: NEA News 27.2 (December 2009) -

This publication is also available in English as: Nuclear Law Bulletin No. 84 (December 2009) - Volume 2009/2

Synopsis

Considéré comme l’ouvrage de référence en la matière, le Bulletin de droit nucléaire est une publication internationale unique en son genre où juristes et universitaires peuvent trouver une information à jour sur l’évolution de ce droit. Publié deux fois par an en anglais et en français, il rend compte du développement des législations dans une soixantaine de pays. Il tient le lecteur informé de la jurisprudence, des décisions administratives, des accords internationaux et des activités réglementaires des organisations internationales, dans le domaine de l’énergie nucléaire.

Les principaux articles de ce numéro portent sur « Le renouveau du nucléaire – Un nouveau droit nucléaire? », « La Directive établissant un cadre communautaire pour la sûreté nucléaire des installations nucléaires » ainsi que « L'harmonisation de la responsabilité civile nucléaire au sein de l'Union européenne ».

This publication is also available in English as: Research and Test Facilities Required in Nuclear Science and Technology -

Synopsis

Les installations expérimentales sont des outils de recherche indispensables au développement des sciences et technologies nucléaires et à l’expérimentation des systèmes et matériaux utilisés actuellement ou qui le seront à l’avenir. Compte tenu des pressions économiques et de la fermeture des installations anciennes, il est à craindre que la capacité à entreprendre les recherches nécessaires au maintien et au développement de la science et de la technologie nucléaires ne soit menacée.

Un groupe d’experts de l’AEN comprenant des représentants de dix pays membres, de l’Agence internationale de l’énergie atomique et de la Commission européenne a examiné la situation des installations de recherche et d’expérimentation opérant dans les domaines d’intérêt du Comité des sciences nucléaires de l’AEN, à savoir : la mesure des données nucléaires, le développement des réacteurs, la diffusion de neutrons, la neutronographie, les systèmes hybrides, la transmutation, le combustible nucléaire, les matériaux, la sûreté, la radiochimie, la séparation et l’utilisation de la chaleur des réacteurs nucléaires pour la production d’hydrogène.

Ce rapport contient l’évaluation détaillée du groupe d’experts sur la situation actuelle des installations de recherche nucléaire, ainsi que des recommandations sur la façon de garantir le développement de ce secteur grâce à la mise en place d’installations modernes de qualité. Il décrit aussi la base de données en ligne établie par le groupe d’experts, qui recense plus de 700 installations.

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: Nuclear Law Bulletin No. 83 (June 2009) -

Synopsis

Considéré comme l’ouvrage de référence en la matière, le Bulletin de droit nucléaire est une publication internationale unique en son genre où juristes et universitaires peuvent trouver une information à jour sur l’évolution de ce droit. Publié deux fois par an en anglais et en français, il rend compte du développement des législations dans une soixantaine de pays. Il tient le lecteur informé de la jurisprudence, des décisions administratives, des accords internationaux et des activités réglementaires des organisations internationales, dans le domaine de l’énergie nucléaire.

Les articles marquants de ce numéro portent sur « Le mécanisme de la conférence d’examen en droit nucléaire : problèmes et perspectives », la « Mise en œuvre et application sur le plan national des traités établissant des zones exemptes d’armes nucléaires » et « Le déclassement d’Asse II : Un fardeau du passé en République fédérale d’Allemagne ».

This publication is also available in English as: NEA News 27.1 (June 2009) -

This publication is also available in English as: Strategic and Policy Issues Raised by the Transition from Thermal to Fast Nuclear Systems -

Synopsis

Le renouveau d'intérêt pour l'énergie nucléaire résultant des préoccupations causées par le changement climatique global et la sécurité d'approvisionnement, qui est susceptible d'entraîner une croissance notable de la production d'électricité nucléaire, rend plus attractifs les réacteurs à neutrons rapides fonctionnant en cycle fermé. La transition entre le parc actuel de réacteurs à neutrons thermiques et des systèmes à neutrons rapides demandera plusieurs décennies et d'importants efforts de RD-D. Cet ouvrage identifie et analyse les questions stratégiques et politiques clés posées par une telle transition et vise à assister les décideurs dans le choix des meilleures approches pour mettre en œuvre des scénarios de transition.

Les sujets traités dans ce livre intéresseront les décideurs des gouvernements et de l'industrie nucléaire ainsi que les spécialistes de l'analyse des systèmes énergétiques nucléaires et des cycles du combustible avancés.

This publication is also available in English as: Annual Report 2008 -

This publication is also available in English as: Summary Report of the CRPPH 50th Anniversary Conference - Committee on Radiation Protection and Public Health (CRPPH), 31 May 2007

Synopsis

Le Comité de protection radiologique et de santé publique (CRPPH) de l’AEN a célébré son 50e anniversaire en mai 2007. Mettant à profit l’expérience accumulée en un demi-siècle, le Comité a saisi cette occasion pour déterminer quels seront, dans les 50 prochaines années, les grands enjeux de la politique et de la réglementation en matière de radioprotection et de leur application. Ce rapport résume les contributions et les analyses des responsables de haut niveau des autorités de sûreté et des organisations internationales de radioprotection qui ont participé à l’événement et ont donné leurs points de vue sur la meilleure façon dont les spécialistes de radioprotection peuvent ensemble relever ces nouveaux défis.

This publication is also available in English as: The NEA Contribution to the Evolution of the International System of Radiological Protection -

Synopsis

Depuis que la Commission internationale de protection radiologique (CIPR) a lancé en 1999 une réflexion collective sur le système de protection radiologique, le Comité de protection radiologique et de santé publique (CRPPH) de l’AEN y a activement contribué par la communication de ses observations et ses points de vue. Les travaux du Comité dans ce domaine ont fait l'objet de huit rapports de groupes d'experts, de sept conférences internationales et de quatre revues critiques approfondies des différentes versions des futures recommandations de la CIPR. Le présent rapport récapitule par ordre chronologique les sujets, points de vue et motifs de préoccupation évoqués par le CRPPH à mesure que la CIPR élaborait les différents projets de ses nouvelles recommandations (parues en décembre 2007 en tant que Publication 103 de la CIPR), ainsi que les réactions de la Commission telles qu'elles transparaissaient des versions qui se suivaient. Cette synthèse présente l'intérêt non seulement d'aider le lecteur à comprendre les thématiques et concepts propres aux nouvelles recommandations, mais aussi pourquoi et comment ont vu le jour les modifications faites aux précédentes recommandations de la Publication 60.

This publication is also available in English as: CSNI Technical Opinion Papers - No. 11 - Better Nuclear Plant Maintenance: Improving Human and Organisational Performance

Synopsis

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.

This publication is also available in English as: CSNI Technical Opinion Papers - No. 10 - The Role of Human and Organisational Factors in Nuclear Plant Modifications

Synopsis

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.

This publication is also available in English as: CSNI Technical Opinion Papers - No. 12 - Research on Human Factors in New Nuclear Plant Technology

Synopsis

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.