Nuclear Energy Publications

This CD-ROM publication gives information on the increased interest of developing countries in nuclear power, which has resulted in intensified efforts in development of small and medium sized reactors (SMRs). Also, in industrialized countries, electricity market deregulation is calling for power generation flexibility that SMRs may offer. Apart from electricity generation, SMRs are of particular interest for non-electrical applications of nuclear energy, such as desalination of seawater and district heating.

This publication gives information on the increased interest of developing countries in nuclear power, which has resulted in intensified efforts in development of small and medium sized reactors (SMRs). Also, in industrialized countries, electricity market deregulation is calling for power generation flexibility that SMRs may offer. Apart from electricity generation, SMRs are of particular interest for non-electrical applications of nuclear energy, such as desalination of seawater and district heating.

CD-ROM

This CD-ROM publication reports on the International Conference on Storage of Spent Fuel from Power Reactors, which gave an opportunity for exchange of information on the state of the art and prospects of spent fuel storage, for discussion of the worldwide situation and the major factors influencing the national policies in this field, and for the identification of the most important directions that national efforts and international co-operation in this area should take.

This publication reports on the International Conference on Storage of Spent Fuel from Power Reactors, which gave an opportunity for exchange of information on the state of the art and prospects for spent fuel storage, for discussion of the worldwide situation and the major factors influencing the national policies in this field, and for the identification of the most important directions that national efforts and international co-operation in this area should take.

The objectives of the symposium were to emphasize the role of nuclear power plant (NPP) life management programmes in assuring a safe and reliable NPP operating cycle, to identify progress in methodological and technological developments for managing ageing processes and understanding degradation mechanisms, and to provide a forum for information exchange on national and international policies and strategies in NPP life management programme development. The proceedings are published on this CD-ROM.

The International Atomic Energy Agency, in cooperation with the World Nuclear Association, the World Energy Council, the International Science and Technology Center and the Electric Utilities Cost Group, organized the International Conference on Innovative Technologies for Nuclear Fuel Cycles and Nuclear Power, held in Vienna from 23 to 26 June 2003. The main objectives of the Conference were to facilitate exchange of information between senior experts and policy makers from Member States and international organizations on important aspects of the development of innovative technologies for future generations of nuclear power reactors and fuel cycles; to create an understanding of the social, environmental and economic conditions that would facilitate innovative and sustainable nuclear technologies; and to identify opportunities for collaborative work between Member States and international organizations and programmes. In addition to 21 oral presentations and 26 poster presentations of accepted papers, talks on specific topics were given by 21 invited speakers from 11 Member States. All relevant aspects of innovative technologies for nuclear fuel cycles and nuclear power were discussed in an open, frank and objective manner. This publication includes an executive summary of the conference and the papers presented.

The ETDE/INIS Joint Thesaurus contains the controlled terminology for indexing all information within the subject scope of both the INIS (International Nuclear Information System) and ETDE (Energy Technology Data Exchange) information systems. The terminology is intended for use in subject description for input or retrieval of information in those systems. The Joint Thesaurus contains over 29000 terms with hierarchies showing their interrelationships. The Thesaurus is the result of continued editing carried out in parallel to the processing of input to the INIS and ETDE Databases, and is one of the most authoritative sources of terminology in the fields of nuclear and energy technology. The present document (in two volumes) supersedes INIS Reference Series No. 13, INIS: Thesaurus (Rev. 38) (1999).

This is the first revision of the INIS/ETDE Joint Thesaurus. It contains 20953 valid descriptors and 8600 forbidden terms, and was last updated in December 2003. The Joint Thesaurus contains the controlled terminology for indexing all information within the subject scope of both the INIS (International Nuclear Information System) and ETDE (Energy Technology Data Exchange) information systems. The terminology is intended for use in the subject description for input of information to or retrieval of information from those systems. The original basis of the terminology found in this thesaurus was the 1969 edition of the Euratom Thesaurus. The structure subsequently given to that terminology was the result of a systematic study performed by subject specialists. Further expansion of the thesaurus terminology was done by ETDE to incorporate information on all forms of energy. The Joint Thesaurus is the result of continued editing carried out in parallel to the processing of the INIS and ETDE databases.

This document defines the subject categories and provides the scope descriptions to be used for categorization of the nuclear literature for the preparation of INIS input by national and regional centers. It is based on an agreement reached between the International Nuclear Information System (INIS) and the Energy Technology Data Exchange (ETDE) on a common scheme of subject categorization that allows for some difference between their systems in subject scope. This document provides the guidance for the application and use of these subject categories and defines the technical subject content of both databases.

This document present the rules, guidelines and procedures to be adopted by centers submitting input to the International Nuclear Information System (INIS) or the Energy Technology Data Exchange (ETDE) and also constitutes a part of the ETDE Procedures Manual. It is a manual for the subject analysis part of input preparation, meaning the selection, subject classification, abstracting and subject indexing of relevant publications, and is to be used in conjunction with the Thesauruses, Subject Categories documents and the documents providing guidelines for the preparation of abstracts.

Occupationally exposed workers need to have a basic awareness and understanding of the risks posed by exposure to radiation and the measures for managing these risks. To assist persons who have a responsibility to provide the necessary education and training of these workers, the series of Practical Radiation Technical Manuals (PRTMs) was created. Radiation measuring instruments are needed in order to detect the presence of ionizing radiation and avoid excessive exposure. The use of appropriate and efficient instruments enables exposures to be controlled and the doses received to be kept as low as reasonably achievable. This manual explains the basic terminology associated with such measuring instruments and describes the principal types, their construction and typical applications in the workplace. It provides information to ensure that the monitoring instrument is appropriate to the task and that the user makes correct interpretations of the results obtained.

Occupationally exposed workers need to have a basic awareness and understanding of the risks posed by exposure to radiation and the measures for managing these risks. To assist persons who have a responsibility to provide the necessary education and training of these workers, the series of Practical Radiation Technical Manuals (PRTMs) was created. Sources of ionizing radiation have a large number of applications in the workplace. The exposures of the individual workers involved may need to be routinely monitored and records kept of their cumulative radiation doses. There are also occasions when it is necessary to retrospectively determine a dose which may have been received by a worker. This manual explains the basic terminology associated with individual monitoring and describes the principal types of dosimeters and other related techniques and their application in the workplace.

This is the twenty-second edition of Reference Data Series No. 1, containing the most recent estimates of energy, electricity and nuclear power trends up to the year 2020. Nuclear data are based on actual statistical data collected by the IAEA’s Power Reactor Information System (PRIS). Energy, electricity and population data for 2001 are estimates based on information from the Department of Economic and Social Affairs of the United Nations.

This is the twenty-third edition of Reference Data Series No. 1, containing the most recent estimates for eight world regions of energy, electricity and nuclear power trends up to the year 2030. Nuclear data are based on actual statistical data collected by the IAEA’s Power Reactor Information System (PRIS). The energy, electricity and population data are estimates based on information from the Department of Economic and Social Affairs of the United Nations.

This annual publication contains estimates of energy, electricity and nuclear power trends up to the year 2030, using a variety of sources, such as the IAEA's Power Reactor Information System and data prepared by the United Nations.

This annual publication contains estimates of energy, electricity and nuclear power trends up to the year 2030, using a variety of sources, such as the IAEA's Power Reactor Information System and data prepared by the United Nations.

This annual publication contains estimates of energy, electricity and nuclear power trends up to the year 2030, using a variety of sources, such as the IAEA's Power Reactor Information System and data prepared by the United Nations.

This is the twenty-second edition of Reference Data Series No. 2, which presents the most recent reactor data available to the Agency. It contains summarized information as of the end of 2001 on: (1) power reactors operating or under construction, and shut down; and (2) performance data on reactors operating in the Agency's Member States, as reported to the Agency. The information is collected by the Agency through designated national correspondents in the Member States. The replies are used to maintain the Agency’s Power Reactor Information System (PRIS).

This is the twenty-third edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2002 on: (1) power reactors operating or under construction, and shut down; and (2) performance data on reactors operating in the IAEA Member States, as reported to the IAEA. The information is collected by the Agency through designated national correspondents in the Member States. The replies are used to maintain the IAEA’s Power Reactor Information System (PRIS).

This is the twenty-fourth edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2003 on: (1) power reactors operating or under construction, and shut down; and (2) performance data on reactors operating in the IAEA Member States, as reported to the IAEA. The information is collected by the Agency through designated national correspondents in the Member States. The replies are used to maintain the IAEA’s Power Reactor Information System (PRIS).

This is the twenty-fifth edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2004 on: (1) power reactors operating or under construction, and shut down; and (2) performance data on reactors operating in the IAEA Member States, as reported to the IAEA. The information is collected by the IAEA through designated national correspondents in the Member States. The replies are used to maintain the IAEA’s Power Reactor Information System (PRIS).

This is the twenty-sixth edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2005 on: (1) power reactors operating or under construction, and shut down; and (2) performance data on reactors operating in the IAEA Member States, as reported to the IAEA. The information is collected by the IAEA through designated national correspondents in the Member States. The replies are used to maintain the IAEA’s Power Reactor Information System (PRIS).

The IAEA has been publishing Regulations for the Safe Transport of Radioactive Material since 1961. Meeting its statutory obligation to foster the exchange and training of scientists and experts in the field of peaceful uses of atomic energy, the IAEA has developed a standardized approach to transport safety training. This training manual is an anchor of the standardized approach to training. It is a compendium of training modules for courses related to the different aspects of safety of transport of radioactive material. Keeping in view the specific needs of the potential users, the manual includes material that can be used for a variety of training programmes of duration ranging from half-a-day to ten days, for specific audiences such as competent authority personnel, public authorities, emergency response personnel and cargo handlers.

This guidebook demonstrates how the designers and operators of future commercial nuclear plants can exploit the reliability and availability of engineering methods and techniques as well as risk based management programmes, developed over the past two decades to augment existing design and operational nuclear plant decision-making capabilities.

This publication provides an overview of the status of post-irradiation examination (PIE) techniques for water reactor fuel assemblies and their components with emphasis given to advanced PIE techniques applied to high burnup fuel. The progress made in non-destructive and destructive PIE techniques used for investigation of water reactor fuel is described. Recent practice in high burnup fuel investigation revealed the importance of advanced PIE techniques, such as 3-D tomography, secondary ion mass spectrometry, laser flash, high resolution transmission, scanning electron microscopy, and image analysis in microstructural studies, for understanding mechanisms of fuel behaviour under irradiation. The importance and needs for in-pile irradiation of samples and rodlets in instrumented rigs were also discussed.

This publication provides an overview of the status of post-irradiation examination (PIE) techniques for water reactor fuel assemblies and their components with emphasis given to advanced PIE techniques applied to high burnup fuel. The progress made in non-destructive and destructive PIE techniques used for investigation of water reactor fuel is described. Recent practice in high burnup fuel investigation revealed the importance of advanced PIE techniques, such as 3-D tomography, secondary ion mass spectrometry, laser flash, high resolution transmission, scanning electron microscopy, and image analysis in microstructural studies, for understanding mechanisms of fuel behaviour under irradiation. The importance and needs for in-pile irradiation of samples and rodlets in instrumented rigs were also discussed.

This TECDOC provides the presented papers and summarizes the discussions at the Technical Committee Meeting on Natural Circulation Data and Methods for Innovative Nuclear Power Plant Design. Light water reactors (LWRs) and heavy water reactors (HWRs) are covered.

This publication reports on the results of two Technical Committee Meetings, which were held to address the trends in spent fuel storage for extended duration and the related potential technological and regulatory impacts.

This publication provides technical advice to those who need to manage disused and spent high activity sources and discusses relevant issues involved. It also provides background information for any possible technical assistance to be provided and serves as a reference for technical staff sent by the IAEA to provide advice to Member States.

This is the second report that addresses results from the Co-ordinated Research Project on Irradiation Enhanced Degradation of Materials in Spent Fuel Storage Facilities. The first report is entitled Durability of Spent Nuclear Fuels and Storage Facility Components in Wet Storage, IAEA-TECDOC-1012. Because of the enhanced importance of wet storage, the scope of the first report was expanded to include both irradiated and unirradiated effects on fuels and facility materials. This second report addresses results of topical studies that are relevant to issues important to materials behaviour in wet storage technology but also involves topics on materials behaviour in dry storage and repository environments, including effects of radiation.

This publication, arising from a Co-ordinated Research Project (CRP), describes the main results and recommendations. The work carried out by the research groups at the participating institutes within the CRP on harmonization and validation of fast reactor thermomechanical and thermohydraulic codes and relations is also included.

This publication addresses the management of the chemical toxicity effects of low and intermediate level radioactive wastes. Consideration of chemical toxicity requires an analysis of its impact on the disposal system performance, and the identification of pre-disposal management technologies that support protection of human health and the environment. The document identifies the nature of chemical toxicity contained in LILW, discusses technical options, performance requirements and regulatory aspects in dealing with chemical toxicity, and presents current technical information on applicable waste processing and disposal technologies.

Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. This publication is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination.

The overall objective is to facilitate the cost-effective implementation of software-based I&C systems in nuclear power plants. This publication reports on the results of a Co-ordinated Research Project (CRP) and gives details of the experience gained in the areas of project management; requirements specifications; use of software explicitly tailored for nuclear applications, use of commercial-off-the-shelf (COTS) systems, generic pre-qualification of systems and components; safety/reliability enhancements; verification and validation; and licensing impact.

Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of Configuration Management (CM) processes as an effective way for limiting configuration errors and related risks. In this report the necessary attributes of a good operational CM are identified. It is recognized and emphasized that CM is one aspect of the overall management system. Nevertheless, this is an important part of managerial activity focused on the compliance of knowledge of the plant personnel, plant documentation and records with the state of the plant technology. The concepts developed in this report present a basic approach to CM, taking into consideration experience gained from organizations and utilities which have successfully implemented partial or full CM programmes and from discussions at meetings organized by the IAEA on the subject.

This publication provides a summary report of a Coordinated Research Project and individual reports of the project participants, compiling results of four years of investigation and development to identify and evaluate different options for combining treatment processes for liquid radioactive waste of complex compositions. The objective of the project was to identify, through the exchange of information and the results of experimental work, specific combined methods for liquid radioactive waste treatment and to define their applicability and efficiency for treatment of different waste streams.

The report presents the proceedings of a Technical Meeting on Fuel Failure in Water Reactors: Causes and Mitigation held in Bratislava, Slovakia in June 2002. Utility and fuel vendor experience in identification of fuel failure causes and on remedies implemented to reduce the number of fuel failures and/or to mitigate fuel failure impact on nuclear power plant operation is analysed and discussed in the report. Emphasis is given to the fuel failure events most frequently observed during the last decade, including grid-to-rod fretting and axial offset anomaly failures in PWRs and severe secondary failures in BWRs. The report also includes information on fuel failure mechanisms and recommendations for fuel failure rate decrease in the near future.

This publication summarizes the results of the IAEA Advisory Group Meeting (AGM) on “Design and Performance of Reactor and Sub-critical Blanket Systems with Lead and Lead-bismuth as Coolant and/or Target Material”. Its purpose was to provide a forum for international information exchange on all the topics relevant to lead and lead-bismuth eutectic cooled critical and subcritical reactors. In addition, the AGM aimed at: (1) finding ways and means to improve international coordination efforts in this area; (2) obtaining advice from Member States with regard to the activities to be implemented in this area by the IAEA, in order to best meet their needs; and (3) laying out plans for effective coordination and support of the R&D activities in this area.

This publication constitutes the final report of the Coordinated Research Project (CRP) on "Potential of Thorium-based Fuel Cycles to Constrain Plutonium and to Reduce Long-term Waste Toxicity" initiated by the IAEA in 1995. The Member States participating in the CRP were: China, Germany, India, Israel, Japan, Republic of Korea, the Netherlands, Russian Federation, and the United States of America. The CRP examined the different fuel cycle options in which plutonium can be recycled with thorium to incinerate plutonium. The potential of the thorium matrix has been examined through computer simulations. Each participant had chosen their own cycle, and the different cycles are compared through certain predefined parameters (e.g., annual reduction of plutonium stockpiles). The radiotoxicity accumulation and the transmutation potential of thorium based cycles for current, advanced and innovative nuclear power reactors are investigated. The research programme was divided into three stages: (1) Benchmark calculations, (2) Optimization of the incineration of plutonium in various reactor types, (3) Assessment of the resulting impact on the waste radiotoxicity.

This publication reports on the results of a Technical Committee Meeting, of which the objectives were: to review the status of R&D activities in the area of hybrid systems for energy generation and transmutation, to discuss specific scientific and technical issues covering the different R&D topics of these systems; and to identify activities that would resolve open R&D issues in this field.

This publication provides advice and technical know-how on the management of disused and spent long lived sealed radioactive sources (LLSRS). It also provides background material for possible technical assistance to developing countries and serves as a reference for technical staff involved with IAEA programmes on the subject.

This publication provides information on methods and practices for evaluating and improving the effectiveness of training and assistance to help nuclear facility managers establish and maintain effective training programmes for nuclear power plant personnel. The principles of effective training provide the overall structure needed to ensure that nuclear training programmes have processes in place to provide significant added value to nuclear power plant operations by improved safety, quality and production.

This publication reports on the International Project on Innovative Nuclear Reactors and Fuel Cycles, referred to as INPRO, which was initiated by the IAEA in 2000. The main objectives of INPRO are: to help to ensure that nuclear energy is available to contribute to fulfilling energy needs in the 21st century in a sustainable manner; and to bring together both technology holders and technology users to consider jointly the international and national actions required to achieve desired innovations in nuclear reactors and fuel cycles.

This publication is one of a series of IAEA publications covering all aspects of the uranium mining industry, from exploration to exploitation, decommissioning and the application of techniques in other non-uranium resources areas.

This publication is directed at senior and middle level managers in nuclear operating organizations. Its objectives are to facilitate the recognition of priority issues with respect to managing human resources, and to provide pragmatic ideas regarding improvements. If not managed effectively, the human resource issues addressed in this publication can result in significant performance problems at nuclear power plants.

One of the current important issues of nuclear power is the long lived waste toxicity problem. A possible way to contribute towards solving this issue is given by the utilization and transmutation of minor actinides and long lived fission products. To this end, the combination of external intensive neutron sources with facilities containing nuclear fuel, so-called hybrid systems, is under investigation in several Member States. The surplus of neutrons in such systems may be used to convert most of the long lived radioactive nuclides into isotopes having a shorter lifetime. There clearly is a need for coordinating the efforts of the various groups involved in this R&D, and also for the exchange of information from nationally or internationally coordinated activities. Consideration of the advantages of hybrid systems, and the wide field of interdisciplinary areas of research involved, clearly shows the need for an international cooperation in this novel R&D area. This publication contains the proceedings of the Advisory Group Meeting on “Review of National Accelerator Driven System (ADS) Programmes”. The scope of the meeting included review of the current R&D programmes in the Member States, and the assessment of the progress in the development of hybrid concepts.

This publication summarizes the results obtained and lessons learned from national case studies carried out under a Coordinated Research Project titled “Case studies to assess and compare different sources in sustainable energy and electricity supply strategies”. It provides a comparison of the costs-benefits and environmental advantages/disadvantages of nuclear power and other electricity generation options in different countries. The report is intended primarily for managers and senior experts in government organizations, research institutes and power utilities who are involved in energy and environmental analysis, interpretation of model results and translation into decision and policy making.

This publication will assist decision makers in countries using nuclear energy for non-power applications to organize their waste management practices. It describes methodologies, criteria and options for the selection of appropriate technologies for processing and storing radioactive waste generated by these applications. A review of both technical and non-technical factors important for decision making and planning, and for implementation of waste management activities at the country and facility levels are presented. Practical recommendations for the selection of particular technologies for different scales of waste generation are made.

This publication summarizes knowledge accumulated in fuel research since the beginning of the 1960s. It concentrates on the "advanced fuels" for the current different types of reactors, including metallic, carbide and nitride fuels for fast reactors, so-called “cold” fuels and fuels to burn excess ex-weapons plutonium in thermal power reactors. Emphasis is given to aspects of fabrication and irradiation behaviour of these fuels. Basic data on essential properties that help to understand the phenomena are also included.

Given a trend towards higher burnup power reactor fuel, the IAEA began an active programme in burnup credit (BUC) with major meetings in 1997 (TECDOC-1013) and 2000 (TECDOC-1241) exploring worldwide interest in using BUC in spent fuel management systems. This publication documents the proceedings of the IAEA’s third major BUC meeting in Madrid in April 2002 on requirements, practices and developments in BUC applications. Fifty-four participants from 18 countries addressed validation of codes and methods, key issues, safety assessment and implementation, and future applications. This meeting encouraged the IAEA to continue its activities on burnup credit including dissemination of related information, given the number of Member States having to deal with increased quantities of spent fuel and extended durations.

High-temperature gas cooled reactor (HTGR) designs present special computational challenges related to their core physics and thermal-hydraulic characteristics. Neutron streaming and double heterogeneities are examples of the core physics challenges, while porous gas flow in a high-temperature ceramic core with the interaction of conduction, convection and radiation regimes characterize thermal-hydraulic challenges. In an effort to address such potential calculation uncertainties, computational results made by various international institutes are reported and code-to-code and code-to-experiment comparisons are made. The experimental data are mainly related to the initial testing of the Japanese HTTR and the Chinese HTR-10. Both are high-temperature gas cooled test reactors. The work is part of an IAEA Co-ordinated Research Project (CRP) with the participation of ten international institutes.

The objective of the project on Optimization of Nuclear Power Plant Overall Performance within the IAEA’s subprogramme of Nuclear Power Planning, Implementation and Performance is to systematically improve the overall performance and competitiveness of nuclear power plants (NPPs) with due regard to safety through the application of technological and engineering best practices, including quality assurance/quality management, and the utilization of relevant databases. As an integrated part of this project, the Technical Working Group on Life Management of NPPs deals with the managerial and engineering aspects of NPP maintenance, its optimization process with special regard to the importance of condition monitoring in maintenance strategies and the contribution of maintenance to managing the lifetime of operating NPPs. This publication was developed in the above framework with the objective to collect and analyse proven maintenance optimization methods and techniques (engineering and organizational) in Member States.

There is significant interest in Member States operating WWER reactors in obtaining information about the highest allowable cladding temperatures for spent fuel assemblies in dry storage facilities. Therefore, special efforts have been made to simulate dry storage tests with WWER-440 fuel rods at the State Scientific Centre of the Russian Federation, Scientific Research Institute for Nuclear Reactors (RIIAR) in Dimitrovgrad, using extra-budgetary funds supplied by the Government of Japan, leading to publication of the results in this publication. The aim is to provide an insight into the maximum spent fuel cladding temperature at the beginning of placement in a dry storage facility, in the context of the pre-cooling time. This publication contains the results of pre-characterization of the rods, descriptions of the tests and the results of characterizations in the two principal temperature regimes.

The scope of this publication covers all of the management activities related to modernization of I&C systems in nuclear power plants, including the evaluation of all I&C systems to determine which can be successfully maintained and which need to be modernized. It also includes large, comprehensive modernization programmes that will modernize a large number of I&C systems, small modernization programmes that will modernize a very few I&C systems, and all of the possibilities in-between. The scope covers highly integrated systems and projects as well as stand-alone systems and projects.

This publication is intended to provide an overview of the most advanced technologies, methods and processes used in the construction and commissioning of recent water cooled nuclear power plants. Information from the following recent nuclear projects has been collected and analysed: Qinshan III Units 1&2 and Lingao Units 1&2 in China, Kashiwazaki-Kariwa Units 6&7 in Japan, Yonggwang Units 5&6 in the Republic of Korea, and Tarapur Units 5&6 in India. To facilitate the readers’ understanding, for each of the construction and commissioning activities reviewed, the publication presents background information, a brief description of the scope, generic good practices and specific examples selected from the collected data. The presentation is focused more on new developments than on providing a full review of all the issues related to construction and commissioning. The main focus of the publication is on-site construction, with only general considerations given to construction activities at manufacturers.

The report is intended to be a source of reference information for interested organizations and individuals, among them decision makers in countries considering implementation of nuclear power programmes. Furthermore, the report is addressed to government officials with an appropriate technical background and to research institutes of countries with existing nuclear programmes that wish to be informed about the global status of advanced light water reactor designs in order to plan their nuclear power programmes, including both research and development efforts and means for meeting future energy needs. The report is also intended to provide the public with unbiased information on nuclear power.

The quality of nuclear power plant (NPP) personnel training is strongly dependent upon the availability of competent instructors. This book is published as a follow-up to Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook, to provide further details concerning the development of instructors for NPP personnel training. This publication has been developed and published to provide practical guidance on various aspects of instructor selection, development and deployment, by quoting actual examples from various countries and operating organizations.

The experience obtained in each individual plant constitutes the most relevant source of information for improving its performance. However, experience of the level of the utility country- and worldwide is also extremely valuable, as there are limitations to what can be learned from in-house experience. Learning from the experience of others is difficult if the information is not harmonized. Therefore, such systems should be standardized and applicable to all types of reactors, satisfying the needs of the broad set of nuclear power plant operators worldwide and allowing experience to be shared internationally. To cope with the considerable amount of information gathered from nuclear power plants worldwide, it is necessary to codify the information facilitating the identification of causes of outages, systems or component failures. Therefore, the IAEA established a sponsored Coordinated Research Project (CRP) on the International Outage Coding System to develop a general, internationally applicable system of coding nuclear power plant outages, providing worldwide nuclear utilities with a standardized tool for reporting outage information. This publication summarizes the results of this CRP and provides information for transformation of the historical outage data into the new coding system, taking into consideration the existing systems for coding nuclear power plant events (WANO, IAEA-IRS and IAEA PRIS) but avoiding duplication of efforts.

This publication is intended to encourage the development and improvement of decommissioning planning and management techniques with the focus on organizational aspects, reduce the duplication of efforts by different parties through transfer of experience and know-how, and provide useful results for those Member States planning or implementing decommissioning projects. In general it can be stated that any decommissioning project can be completed without any deleterious effects on the safety of the workforce and the public or any identifiable impact on the environment. However, timeliness and cost effectiveness are not always optimal. It has been noted on several occasions that the major weakness in decommissioning projects (as well as in other industrial projects) is often not the lack of technologies, but rather poor planning and management. This publication is intended to stimulate awareness of the need for early and efficient planning and to foster developments in management and organization in association with planned or ongoing decommissioning projects. A companion report on Organization and Management for Decommissioning of Large Nuclear Facilities was published by the IAEA in 2000 (Technical Reports Series No. 399) which provides generic guidance on organizational and management aspects. This publication is complementary to the existing publication in that it highlights practical experience – in particular, typical issues, evidence of poor management, undue delays and lack of timely funding – and distils lessons learned from this experience.

Intercomparison and validation of computer codes used in different countries for thermohydraulics safety analysis of heavy water reactors (HWRs) enhances confidence in the predictions made by these codes. A set of reliable experimental data is necessary for conducting such intercomparison and validation exercises. Experimental results from a large loss of coolant accident (LOCA) test simulating HWR LOCA behaviour that was conducted by Atomic Energy of Canada Ltd (AECL) was selected for this validation project. This report provides a comparison of the results obtained from six participating countries, utilizing four different computer codes. General conclusions are reached and recommendations made.

In situ leach (ISL) mining of uranium involves injecting mild acidic or alkaline chemicals through surface boreholes into permeable, uranium-bearing sandstones. The chemicals dissolve the uranium, and the uranium-bearing solutions are pumped to the surface through a second set of boreholes. ISL mining of uranium totalled 6410 tonnes of uranium in 2002, and accounted for 18% of worldwide uranium production. Seven countries reported ISL production in 2002, and other countries are considering the potential for developing an ISL capability, as ISL has economic and environmental advantages for producing uranium from carefully selected deposits. This publication contains 26 papers on various aspects of ISL mining including the geology of ISL-amenable sandstone deposits, case histories of ISL production using leaching solutions of varying chemistry and finally post-mining rehabilitation of ISL projects. The papers were presented at a meeting held in Beijing, China, in 2002, attended by 59 scientists from 18 countries and one international organization (OECD/NEA). Attendees at the meeting also toured one of China’s ISL operations, a description of which is included in this publication.

The objective of this publication is to highlight the importance of the early establishment of a comprehensive records system to manage primary level information (PLI) as an integrated set of information, not merely as a collection of information, throughout all the phases of radioactive waste management. The information presented in this publication will assist Member States in ensuring that waste and repository records, relevant for retention after repository closure, are generated, identified, reviewed and actively managed during pre-closure phases so that they are available and useable at the appropriate time. This publication addresses the establishment and management of the PLI set up to the point of closure of a repository. Specifically, it (1) describes the importance of establishing a coordinated, integrated and well-managed PLI set, (2) provides a basic overview of the components of a PLI set, and (3) provides general guidance on the management of and responsibility for the PLI set.

This publication provides information on experiences gained in retaining the knowledge needed to design, operate and maintain nuclear power plants (NPPs) in IAEA Member States in the context of the ageing of the nuclear workforce. Information is provided on effective methods for transfer of knowledge in NPP operating organizations along with selected examples of proven management strategies and initiatives. Awareness and use of this information can assist NPP operating organizations in dealing with the challenges posed by retirement of the current NPP workforce and recruitment of new personnel.

This publication describes strategies for improving the effectiveness of in-service inspection (ISI). The role of ISI in maintaining or improving safety and the relationship of ISI improvement to cost are examined. The strategies for improving ISI effectiveness discussed in this publication consider the entire framework of ISI, including effective selection of the proper scope of inspection and the effectiveness of non-destructive examination as demonstrated through inspection qualification programmes. Improving the effectiveness of ISI in an economical and organized way requires adoption of a strategy that meets the specific objectives of each plant owner. Several such strategies are considered.

The goal of this publication is to provide the latest information on ageing, obsolescence and performance monitoring of those items of instrumentation and control (I&C) equipment that are classified as safety equipment and/or safety related equipment, are operated in harsh environments in NPPs, and are important to plant life extension not only for normal operation but also, and more importantly, for post-accident service. In achieving this goal, this publication identifies the key I&C components of interest that are expected to function well throughout the life of a plant, including the extended life.

Mining and milling of uranium ores has been undertaken in many places around the world, resulting in large volumes of mining/milling residues with low activity concentrations of long lived nuclides that often have been disposed of in a haphazard fashion. This report summarizes the current state of the art of uranium mill tailings disposal and the results from an IAEA Coordinated Research Project (CRP) on technologies and strategies for their long term stabilization. The aim of the CRP was to develop conceptual and technical solutions that render tailings more inert over prolonged time spans, that render impounded materials and engineered structures stable over prolonged time spans, that minimize the need for active maintenance, and that are technically and economically feasible. The emphasis was on solutions that can be applied retrospectively, i.e. in a restoration/remediation context. It was recognized, however, that these objectives cannot be met by engineering design only, but must also involve appropriate management and planning procedures.

This report describes the outcome of a successfully completed National Technical Cooperation Project, ARM/0/004, entitled Energy and Nuclear Power Planning Study (ENPP) for Armenia, covering the period up to 2020. The main objectives of the project were to contribute to the development of a national energy master plan and assess the future role of nuclear power in Armenia by providing proven methodologies and building institutional capacities for analysing different energy options, and to perform an ENPP study. Assisted by the IAEA, a team of local experts conducted the study over a period of two years. The national team conducted a very detailed analysis of the energy issues, and constructed and evaluated various scenarios for future development of the energy sector in Armenia, using the IAEA’s energy planning models. Finally, recommendations on future energy projects and policy were prepared which were used by the national authorities in the formulation of the ENPP for Armenia.

Given the present slowdown in many Member States of fast reactor technology development, and the concomitant retirement of many of the developers of this technology, data retrieval and knowledge preservation efforts in this area are particularly important. Operational experience constitutes an important aspect of any fast reactor knowledge base. It is within this context that the IAEA convened a Topical Technical Meeting on Feedback from Operational and Decommissioning Experience with Fast Reactors. The present publication presents the proceedings of this meeting, which was held from 11 to 15 March 2002 at CEA, Cadarache, France.

The objectives of this publication are to review the safety philosophy for the primary coolant pipe (PCP) rupture event in pool type liquid metal fast reactors (LMFRs), to assess the structural reliability of the PCP and the probability of rupture under different conditions (with/without in-service inspection), to review the classification of the PCP rupture event in the design basis/beyond design basis categories and discuss the applicable design safety limits, to assess the need for consequential analysis such as pipe whip effects, primary pump seizure and multiple pipe rupture, and, last but not least, to present the results of analyses of the event per se for flows and/or temperatures and improved design concepts for minimizing the consequences to the core.

This publication reports on the comprehensive study of Lithuania’s future energy supply strategies taking into consideration necessary measures being implemented in the energy sector in accordance with the accession to full membership of the European Union. Within this context, the study investigates the future development of the Lithuanian electricity/heat supply sector and the impacts on energy supply security and environmental effects of a closure of the Ignalina nuclear power plant by 2009, a condition stipulated by the European Union. The publication describes the application of the IAEA energy models: the Model for Analysis of Energy Demand (MAED) and the Model for Energy Supply Strategy Alternatives and their General Environmental Impacts (MESSAGE), in the context of the Lithuanian energy system, in order to assess the financial, economic and environmental implications of the various development scenarios during the period up to 2025. As a result, a set of future development strategies has been analysed, prioritized and ranked according to their performance indicators with respect to investment requirements, air emission burden and fuel import dependence. For each proposed strategy, a list of best candidate projects for future electricity/heat supply systems has been identified for consideration by policy makers.

This report describes all of the research work undertaken as part of the IAEA coordinated research project on hydrogen and hydride induced degradation of the mechanical and physical properties of zirconium based alloys, and includes a review of the state of the art in understanding crack propagation by delayed hydride cracking (DHC), and details of the experimental procedures that have produced the most consistent set of DHC rates reported in an international round-robin exercise to this date.

Safety analysis and operational experience consistently indicate that human error is the greatest contributor to the risk of a severe accident in a nuclear power plant. Subsequent to the Three Mile Island accident, major changes were made internationally to reduce the potential for human error through improved procedures, information presentation and training of operators. The use of full scope simulators in the training of operators is an essential element of these efforts to reduce human error. In cases where a ‘replica’ plant-referenced full scope simulator is not available, it may be necessary for operators to receive their training with a computer simulation or to travel to another plant that is similar to their plant and has a simulator. This publication has been developed and published to provide information and practical guidance on various aspects of the use of control room simulators, by quoting actual examples from various Member States.

This report discusses in detail the necessary prerequisites, processes involved and applicability of ‘non-intervention’ as a strategy for dealing with radioactive contamination. Particular emphasis is placed on modelling tools as an integral element of monitored natural attenuation (MNA). It provides a comprehensive critique of the applicability of MNA and explores its limits. While MNA is de facto relied upon in many instances where a contamination cannot be completely removed to an engineered repository, it is emphasized that ’non-intervention’ is not equivalent to a ‘do nothing’ option. In order to rely on MNA safely, a thorough understanding of the site and the migration behaviour of the contaminants in the given environment is needed, which is gained by a comprehensive site investigation. This report complements other recent reports on remediation techniques and strategies with a less invasive concept.

This report presents the proceedings of the Technical Meeting on Improved Fuel Pellet Materials and Designs held in Brussels, Belgium, in October 2003. The meeting focused on fabrication and design tools to influence, to some extent, and ensure desirable in-pile fuel properties. Emphasis was placed on the analysis of fuel characteristics at high burnup, including thermal behaviour, fission gas retention and release, pellet–cladding interaction and pellet–cladding mechanical interaction. Specific features of large grain size UO2, MOX and urania-gadolinia fuels with and without additives were considered in detail. A CD-ROM is also included.

Treatment and control of the liquid effluents produced during uranium mining and milling operations is an integral part of environmental project management. Research has continued to add to the large body of science that has been built up around the treatment of radioactive and non-radioactive effluents to minimize their long term environmental impact. The objective of the meetings on which this publication is based was to exchange information on active effluent treatment technologies that have application during operations and passive treatment techniques such as constructed wetlands and use of microorganisms that are applicable during project reclamation and long term care and maintenance. The papers included in this publication describe effluent treatment case histories from active uranium mining and processing operations. There are also papers that describe effluent treatment research on both active and passive systems that have potential application under a wide range of operating and post-operational conditions.

Globalization has led to a growth in importance of the uranium production industries of the world’s developing countries. Uranium supply from these countries could be increasingly important in satisfying worldwide reactor requirements over time. Along with the increasing contribution to worldwide uranium supply, the environmental impact of uranium production in developing countries has come under increasing scrutiny from the nuclear power industry, the end users of this supply, and from communities affected by uranium mining and processing. The papers presented at the meeting on Developments in Uranium Resources, Production, Demand and the Environment provide an important overview of uranium production operations and of their environmental consequences in developing countries, as well as offering insight into future production plans and potential.

Assessment of the potential environmental impact of an in situ leach (ISL) project is the first step in the permission and licensing process. An Environmental Impact Assessment (EIA) serves as the basis for preparing an Environmental Impact Statement (EIS), which in turn identifies the potential environmental and socioeconomic impact of a proposed project and outlines measures to mitigate this impact. The EIS review process serves to inform the public about a proposed project as well as to provide regulatory agencies wit