Nuclear Energy Publications
This comprehensive collection of publications issued by the Department of Nuclear Energy gives you access to over 2 000 TECDOCs, conference proceedings, technical reports, and other nuclear energy-related publications. Where available, publications can be downloaded in PDF and/or ordered from the IAEA's Publications Section.
You can browse through all publications listed below, or find individual documents in your area of interest using the search function on the left-side menu.
CN-122/CD
ISBN: 92-0-109505-8
Publication Date: 22-9-2005
Subject Classification: 0700 - Nuclear power
IAEA-CNPP/2002/CD
ISBN: 92-0-110103-1
Publication Date: 24-4-2003
Subject Classification: 0700 - Nuclear power
IAEA-CNPP/2003/CD
ISBN: 92-0-104604-9
Publication Date: 4-5-2004
Subject Classification: 0603 - Nuclear power plants
IAEA-CNPP/2003/P
ISBN: 92-0-106904-9
Publication Date: 10-6-2004
Subject Classification: 0700 - Nuclear power
IAEA-CSP-10/P
Publication Date: 24-4-2002
Subject Classification: 0801 - Uranium ore processing
IAEA-CSP-14/CD
ISBN: 92-0-135902-0
Publication Date: 19-11-2002
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.
Subject Classification: 0703 - Reactor technology
IAEA-CSP-14/P
ISBN: 92-0-114802-X
Publication Date: 10-9-2002
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.
Subject Classification: 0703 - Reactor technology
IAEA-CSP-15/CD
ISBN: 92-0-139502-7
Publication Date: 9-12-2002
CD-ROM
Subject Classification: 0804 - Waste management
IAEA-CSP-20/CD
ISBN: 92-0-109803-0
Publication Date: 17-11-2003
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.
Subject Classification: 0602 - Fuel fabrication and storage; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management
IAEA-CSP-20/P
ISBN: 92-0-109603-8
Publication Date: 13-10-2003
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.
Subject Classification: 0803 - Spent fuel management
IAEA-CSP-21/CD
ISBN: 92-0-116403-3
Publication Date: 12-3-2004
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.
Subject Classification: 0702 - Nuclear power operations
IAEA-CSP-24/P
ISBN: 92-0-110704-8
Publication Date: 28-1-2005
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.
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA-ETDE/INIS-1
ISBN: 92-0-115002-4
Publication Date: 9-9-2002
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).
Subject Classification: 1200 - International Nuclear Information System
IAEA-ETDE/INIS-1 (Rev. 1)
ISBN: 92-0-105604-4
Publication Date: 20-5-2004
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.
Subject Classification: 1200 - International Nuclear Information System
IAEA-ETDE/INIS-2
ISBN: 92-0-112902-5
Publication Date: 1-8-2002
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.
Subject Classification: 1200 - International Nuclear Information System
IAEA-ETDE/INIS-3
ISBN: 92-0-115102-0
Publication Date: 28-10-2002
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.
Subject Classification: 1200 - International Nuclear Information System
IAEA-PRTM-1 (Rev. 1)
Publication Date: 18-5-2004
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.
Subject Classification: 0609 - Radiation protection
IAEA-PRTM-2 (Rev. 1)
Publication Date: 18-5-2004
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.
Subject Classification: 0609 - Radiation protection
IAEA-RDS-1/22
ISBN: 92-0-116902-7
Publication Date: 13-9-2002
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 IAEAs 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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/23
ISBN: 92-0-109203-2
Publication Date: 10-9-2003
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 IAEAs 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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/24
ISBN: 92-0-109004-8
Publication Date: 8-9-2004
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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/25
ISBN: 92-0-108705-5
Publication Date: 24-8-2005
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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/26
ISBN: 92-0-107006-3
Publication Date: 8-9-2006
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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-2/22
ISBN: 92-0-112102-4
Publication Date: 9-8-2002
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 Agencys Power Reactor Information System (PRIS).
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/23
ISBN: 92-0-106703-8
Publication Date: 18-9-2003
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 IAEAs Power Reactor Information System (PRIS).
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/24
ISBN: 92-0-108204-5
Publication Date: 19-7-2004
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 IAEAs Power Reactor Information System (PRIS).
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/25
ISBN: 92-0-104205-1
Publication Date: 24-8-2005
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 IAEAs Power Reactor Information System (PRIS).
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/26
ISBN: 92-0-106906-5
Publication Date: 10-7-2006
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 IAEAs Power Reactor Information System (PRIS).
Subject Classification: 0700 - Nuclear power
IAEA-TCS-01/03
Publication Date: 28-4-2003
Subject Classification: 0606 - Transport of radioactive material
IAEA-TCS-01/04
Publication Date: 20-10-2006
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.
Subject Classification: 0606 - Transport of radioactive material
IAEA-TCS-21
Publication Date: 29-9-2003
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TCS-22
Publication Date: 29-9-2003
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TCS-23
Publication Date: 9-10-2003
Subject Classification: 0703 - Reactor technology
IAEA-TCS-27
Publication Date: 24-10-2005
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1264
Publication Date: 8-2-2002
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1273
Publication Date: 19-4-2002
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1277
Publication Date: 8-4-2002
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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1277/CD
Publication Date: 5-4-2002
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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1279
Publication Date: 9-4-2002
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1281
Publication Date: 9-4-2002
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1284
Publication Date: 27-5-2002
Subject Classification: 0700 - Nuclear power
IAEA-TECDOC-1286
Publication Date: 22-5-2002
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1288
Publication Date: 9-7-2002
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1289
ISBN: 92-0-113602-1
Publication Date: 6-8-2002
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1290
Publication Date: 22-5-2002
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1293
Publication Date: 11-7-2002
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.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1296
Publication Date: 6-8-2002
Subject Classification: 0801 - Uranium ore processing; 0804 - Waste management
IAEA-TECDOC-1299
ISBN: 92-0-112802-9
Publication Date: 25-7-2002
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1301
ISBN: 92-0-114502-0
Publication Date: 23-9-2002
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.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1303
ISBN: 92-0-112702-2
Publication Date: 25-7-2002
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-1304
ISBN: 92-0-112602-6
Publication Date: 6-8-2002
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1305
ISBN: 92-0-113002-3
Publication Date: 30-8-2002
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-1306
ISBN: 92-0-113102-X
Publication Date: 30-8-2002
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1308
ISBN: 92-0-115302-3
Publication Date: 24-9-2002
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1309
ISBN: 92-0-114402-4
Publication Date: 10-9-2002
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1315
ISBN: 92-0-117002-5
Publication Date: 10-10-2002
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1316
ISBN: 92-0-113802-4
Publication Date: 22-1-2003
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.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1318
ISBN: 92-0-118302-X
Publication Date: 3-12-2002
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1319
ISBN: 92-0-114202-1
Publication Date: 11-11-2002
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1320
ISBN: 92-0-114602-7
Publication Date: 19-11-2002
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1322
ISBN: 92-0-117802-6
Publication Date: 11-11-2002
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1323
ISBN: 92-0-118202-3
Publication Date: 3-12-2002
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1325
ISBN: 92-0-119802-7
Publication Date: 22-1-2003
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.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1326
ISBN: 92-0-117602-3
Publication Date: 8-1-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1327
ISBN: 92-0-119302-5
Publication Date: 13-12-2002
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-1328
ISBN: 92-0-119902-3
Publication Date: 22-1-2003
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.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1335
ISBN: 92-0-100503-2
Publication Date: 13-2-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1336
ISBN: 92-0-100903-8
Publication Date: 10-2-2003
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.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1343
ISBN: 92-0-102703-6
Publication Date: 8-5-2003
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1345
ISBN: 92-0-101703-0
Publication Date: 28-3-2003
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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1348
ISBN: 92-0-101503-8
Publication Date: 17-6-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1349
ISBN: 92-0-103203-X
Publication Date: 15-5-2003
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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1356
ISBN: 92-0-108103-0
Publication Date: 18-9-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1357
ISBN: 92-0-105403-3
Publication Date: 19-6-2003
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.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1358
ISBN: 92-0-108203-7
Publication Date: 23-9-2003
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.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1362
ISBN: 92-0-105503-X
Publication Date: 19-6-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1363
ISBN: 92-0-108303-3
Publication Date: 18-9-2003
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.
Subject Classification: 0401 - Uranium geology, exploration and mining
IAEA-TECDOC-1364
ISBN: 92-0-105803-9
Publication Date: 17-7-2003
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.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1365
ISBN: 92-0-106803-4
Publication Date: 30-7-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1370
ISBN: 92-0-109303-9
Publication Date: 1-9-2003
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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1371
ISBN: 92-0-108803-5
Publication Date: 9-10-2003
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.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1374
ISBN: 92-0-110303-4
Publication Date: 9-10-2003
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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1378
ISBN: 92-0-111203-3
Publication Date: 26-11-2003
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 IAEAs 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.
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA-TECDOC-1382
ISBN: 92-0-116203-0
Publication Date: 29-1-2004
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1383
ISBN: 92-0-112703-0
Publication Date: 21-1-2004
The objective of the project on Optimization of Nuclear Power Plant Overall Performance within the IAEAs 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.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1385
ISBN: 92-0-103704-X
Publication Date: 3-6-2004
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.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1389
ISBN: 92-0-116103-4
Publication Date: 26-3-2004
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1390
ISBN: 92-0-103804-6
Publication Date: 27-4-2004
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1391
ISBN: 92-0-104804-1
Publication Date: 29-7-2004
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1392
ISBN: 92-0-105204-9
Publication Date: 3-8-2004
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.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1393
ISBN: 92-0-116003-8
Publication Date: 3-6-2004
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.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1394
ISBN: 92-0-104404-6
Publication Date: 17-6-2004
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.
Subject Classification: 0603 - Nuclear power plants; 0701 - Nuclear power planning and economics; 0804 - Waste management
IAEA-TECDOC-1395
ISBN: 92-0-106004-1
Publication Date: 19-10-2004
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.
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-1396
ISBN: 92-0-103104-1
Publication Date: 8-9-2004
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 Chinas ISL operations, a description of which is included in this publication.
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-1397
ISBN: 92-0-107904-4
Publication Date: 14-7-2004
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1398
ISBN: 92-0-107104-3
Publication Date: 29-7-2004
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.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
IAEA-TECDOC-1399
ISBN: 92-0-107704-1
Publication Date: 29-6-2004
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.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1400
ISBN: 92-0-108104-9
Publication Date: 12-8-2004
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.
Subject Classification: 0603 - Nuclear power plants; 0704 - Quality assurance
IAEA-TECDOC-1402
ISBN: 92-0-108804-3
Publication Date: 25-10-2004
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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1403
ISBN: 92-0-108904-X
Publication Date: 19-10-2004
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.
Subject Classification: 0601 - Uranium mining and milling
IAEA-TECDOC-1404
ISBN: 92-0-109204-0
Publication Date: 31-8-2004
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 IAEAs 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.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1405
ISBN: 92-0-107804-8
Publication Date: 31-8-2004
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.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1406
ISBN: 92-0-109104-4
Publication Date: 31-8-2004
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.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
IAEA-TECDOC-1408
ISBN: 92-0-110004-3
Publication Date: 3-11-2004
This publication reports on the comprehensive study of Lithuanias 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.
Subject Classification: 0701 - Nuclear power planning and economics; 1300 - Environment
IAEA-TECDOC-1410
ISBN: 92-0-110504-5
Publication Date: 8-11-2004
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1411
ISBN: 92-0-110604-1
Publication Date: 18-11-2004
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.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1413
ISBN: 92-0-112204-7
Publication Date: 15-10-2004
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.
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
IAEA-TECDOC-1416
ISBN: 92-0-111404-4
Publication Date: 2-12-2004
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, pelletcladding interaction and pelletcladding 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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-1419
ISBN: 92-0-112304-3
Publication Date: 14-2-2005
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.
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-1425
ISBN: 92-0-112904-1
Publication Date: 4-3-2005
Globalization has led to a growth in importance of the uranium production industries of the worlds 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.
Subject Classification: 0401 - Uranium geology, exploration and mining; 0801 - Uranium ore processing; 1300 - Environment
IAEA-TECDOC-1428
ISBN: 92-0-113004-X
Publication Date: 22-6-2005
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 with assurance that ISL technology will comply with environmental standards, and that project sites can be rehabilitated to pre-mining use. This publication provides a step-by-step description of project parameters that must be addressed in conducting an EIA and preparing an EIS. It also includes EIA/EIS case histories for current operations in Australia, the Czech Republic, Kazakhstan and the United States of America. The publication will be useful to companies considering the development of ISL projects and to regulatory personnel who are responsible for writing environmental regulations and licensing ISL projects.
Subject Classification: 0401 - Uranium geology, exploration and mining; 1300 - Environment
IAEA-TECDOC-1433
ISBN: 92-0-101405-8
Publication Date: 19-4-2005
This publication provides an overview of remote technology applications to spent fuel management within the scope of the fuel cycle back end. Remote systems technology has been extensively applied to a variety of work in spent fuel management facilities with such benefits as dose reduction to workers, enhancement of operational performance or reliability and saving of labour costs. In recognition of the beneficial applications of remote technology in spent fuel management, the IAEA has provided information on state-of-art developments and practices.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1434
ISBN: 92-0-116304-5
Publication Date: 17-2-2005
The main objectives of INPRO are to: help ensure that nuclear energy is available to contribute towards fulfilling energy needs in the 21st century in a sustainable manner; and 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. Within INPRO the future energy demand and supply was explored and several scenarios were identified. The following requirement for energy supply will play a crucial role: sustainability of the way the energy supply will be realized. Fulfilling the growing need for energy in developing countries is also an important issue. On the basis of scenarios for the next fifty years, requirements for the different aspects of the future of nuclear energy systems, such as those on economics, environment, safety, waste, proliferation resistance and infrastructure, have been identified as well as a methodology developed to assess innovative nuclear systems and fuel cycles. On the basis of this assessment, the need for innovations in existing nuclear technology, to be achieved via research, development and demonstration, can be defined. To facilitate the deployment of innovative nuclear systems, different aspects of the infrastructure, technical as well as institutional, also have been reviewed, and recommendations for changes are made to anticipate the main developments worldwide, such as ongoing globalization.
Subject Classification: 0700 - Nuclear power; 0800 - Nuclear fuel cycle and waste management
IAEA-TECDOC-1435
ISBN: 92-0-101605-0
Publication Date: 24-5-2005
This publication has been developed under the Coordinated Research Project (CRP) entitled: Surveillance Programme Results Application to Reactor Pressure Vessel Integrity Assessment. This publication provides a summary of master curve fracture toughness test results on small surveillance type specimens of the IAEA reference material JRQ and other national steels from numerous laboratories around the world. These results were a key ingredient used in the development of the guidance given in IAEA Technical Reports Series No. 429, Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity. This publication has been written to allow utility engineers and scientists to directly measure fracture toughness and apply the results using the master curve approach for RPV structural integrity assessment.
Subject Classification: 0704 - Quality assurance
IAEA-TECDOC-1441
ISBN: 92-0-103305-2
Publication Date: 15-8-2005
The goal of this publication is to investigate and understand the mechanism of the deterioration effect in radiation embrittlement of reactor pressure vessel steels of NiCrMoV or MnNiCrMo types with a high nickel content (>1.5 wt%) in nuclear power plants. Eleven institutes from eight countries and the European Union participated in the Coordinated Research Project (CRP) entitled Mechanism of Nickel Effect in Radiation Embrittlement of RPV Material, and six institutes conducted the irradiation experiments with the CRP materials. In addition to the irradiation and testing of those materials, irradiation experiments with various national steels were conducted. This publication provides the results of all the data obtained by the participants. It is generally accepted that the presence of nickel in RPV steels increases their sensitivity to neutron induced embrittlement even at low phosphorus and copper concentrations.
Subject Classification: 0704 - Quality assurance
IAEA-TECDOC-1442
ISBN: 92-0-105605-2
Publication Date: 15-8-2005
The IAEA International Database on RPV Materials (IDRPVM) is used for prediction and analysis of radiation embrittlement of WWER-440 reactor pressure vessel (RPV) materials. These guidelines will be used for assessment of irradiation embrittlement of RPV ferritic materials as a result of degradation during operation. Two approaches, i.e. transition temperatures based on Charpy impact notch toughness as well as those based on static fracture toughness tests, are used to develop the prediction formulas for radiation embrittlement of RPVs of WWER-440 nuclear power plants.
Subject Classification: 0702 - Nuclear power operations; 0704 - Quality assurance
IAEA-TECDOC-1444
ISBN: 92-0-102505-X
Publication Date: 15-8-2005
This publication presents the results of an IAEA Coordinated Research Project (CRP) on Optimization of the Coupling of Nuclear Reactors and Desalination Systems. The overall scope of the CRP was to encompass research and development projects focused on optimized coupling of nuclear and desalination systems in the following areas: nuclear reactor design intended for coupling with desalination systems; optimization of thermal coupling of nuclear steam supply systems and desalination systems; performance improvement of desalination systems for coupling; and advanced desalination technologies for nuclear desalination. A total of nine nuclear reactors were examined for optimal coupling with desalination systems within this CRP. They are all of the water cooled reactor type and are in various degrees of development. The commercial seawater desalination processes which are proven and reliable for large scale production of desalted water are multi-stage flash (MSF) and multi-effect distillation (MED) for distillation processes and reverse osmosis (RO) for membrane processes, as well as hybrid technologies such as MSF-RO and MED-RO. Different coupling options between the above nuclear and desalination technologies have been investigated within the CRP and were optimized with respect to safety, operational flexibility, reliability/availability and economics.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1450
ISBN: 92-0-103405-9
Publication Date: 14-7-2005
There has been significant interest among Member States in developing advanced and innovative technologies for safe, proliferation resistant and economically efficient nuclear fuel cycles, while minimizing waste and environmental impacts. This publication provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle. The aim is to address the benefits and challenges faced at the front and back ends of the thorium fuel cycle, highlighting fuel fabrication, reprocessing and waste management. In addition, this publication provides an insight into the reasons for renewed interest in the thorium fuel cycle, different implementation scenarios and options for the thorium cycle, and an update of the information base on thorium fuels and fuel cycles.
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA-TECDOC-1451
ISBN: 92-0-103205-6
Publication Date: 9-6-2005
Design and technology development for small and medium sized reactors (SMRs) is ongoing in many countries, and there are growing expectations of increased support from the IAEA to interested Member States in the definition of common technology and infrastructure development needs and in the coordination of international R&D efforts for such reactors. This publication presents a variety of innovative water cooled, gas cooled, liquid metal cooled and non-conventional SMR designs developed worldwide, and examines the technology and infrastructure development needs that may be common to several concepts or lines of such reactors. This publication also gives an updated definition of small reactors without on-site refuelling and a preliminary review of the passive safety design options for SMRs.
Subject Classification: 0603 - Nuclear power plants; 0604 - Research reactors; 0703 - Reactor technology
IAEA-TECDOC-1452
ISBN: 92-0-105405-X
Publication Date: 15-8-2005
Arms control agreements between some Nuclear Weapon States have led to the dismantling of many of the nuclear weapons in their military stockpiles, which in turn have produced stockpiles of excess weapons-grade high enriched uranium (HEU) from the dismantled weapons. Considering the proliferation potential of HEU, the management, control and disposition of this fissile material has become a primary focus of nuclear non-proliferation efforts worldwide. To lessen the proliferation threat of excess HEU stockpiles, the USA agreed to purchase several tonnes of excess Russian HEU down-blended to low enriched uranium (LEU). Proliferation concerns about HEU have also resulted in a global effort to convert research reactors from HEU to LEU fuel and to minimize civilian use of HEU. This publication addresses HEU management declared excesses, non-proliferation programmes and options for the use of HEU stockpiles, including disposition programmes. Also addressed are the influence of LEU derived from surplus HEU on the global market for uranium, technical issues associated with utilization and the disposition of HEU.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1454
ISBN: 92-0-105105-0
Publication Date: 26-8-2005
This publication, the proceedings of a meeting, covers topics including the impact of hydraulic loadings on fuel assembly (FA) performance, FA bow and control rod drop kinetics, vibrations and rod-to-grid wear and fretting, and evaluation and modelling of accident (mainly seismic) conditions. These proceedings are presented as a book with an attached CD-ROM. The first part of the CD-ROM repeats the papers presented at the meeting and the second part contains the Appendix with the original slides (in PowerPoint) converted into pdf format.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology; 0802 - Fuel fabrication and performance
IAEA-TECDOC-1463
ISBN: 92-0-108005-0
Publication Date: 2-11-2005
The uranium industry is in a period of transition. In Europe, the industry is in transition from uranium production to site rehabilitation. The WISMUT project in Germany, which is featured in this publication, is the largest and one of the most advanced rehabilitation projects in the world. By contrast, other countries such as China, India and Argentina are expanding their industries to meet growing uranium demand. Activities in these countries, which are also described in this publication, range from new project licensing to the application of new technology to increase productivity and lower costs at existing operations. Changes within the uranium industry are nowhere more evident than in the marketplace, where the price of uranium has more than doubled in the past two years. There is a discussion of the reasons for this price rise and of the adequacy of production capacity to meet reactor uranium requirements.
Subject Classification: 0401 - Uranium geology, exploration and mining; 1300 - Environment
IAEA-TECDOC-1467
ISBN: 92-0-108805-1
Publication Date: 23-9-2005
The management of spent fuel arising from nuclear power production is a crucial issue for the sustainable development of nuclear energy. The IAEA has issued several publications in the past that provide technical information on the global status and trends in spent fuel reprocessing and associated topics, and one reason for this present publication is to provide an update of this information which has mostly focused on the conventional technology applied in the industry. However, the scope of this publication has been significantly expanded in an attempt to make it more comprehensive and by including a section on emerging technologies applicable to future innovative nuclear systems, as are being addressed in such international initiatives as INPRO, Gen IV and MICANET. In an effort to be informative, this publication attempts to provide a state-of-the-art review of these technologies, and to identify major issues associated with reprocessing as an option for spent fuel management. It does not, however, provide any detailed information on some of the related issues such as safety or safeguards, which are addressed in other relevant publications.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1469
ISBN: 92-0-111105-3
Publication Date: 10-11-2005
The IAEA offers its Member States a comprehensive programme of technical assistance and cooperation, which covers many diverse areas related to peaceful uses of nuclear energy. In the area of energy planning, the IAEA provides assistance to Member States to strengthen national capabilities for elaborating sustainable patterns of energy supply and use. This publication is a successful example of implementing an energy planning project in Mexico. It can serve as a guideline for designing and implementing similar projects in other countries, addressing the economic, social and environmental issues of energy sector development.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1474
ISBN: 92-0-110605-X
Publication Date: 8-12-2005
An important new approach incorporated into several advanced LWR and HWR designs involves the use of passive safety systems. This approach is expected to provide a very high level of safety and improved economics through design simplification. Considering the weak driving forces of passive systems based on natural circulation, careful design and analysis methods must be employed to ensure that the systems perform their intended function. This publication describes the present state of knowledge of natural circulation in water cooled nuclear power plants and passive system reliability. It presents extensive information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1478
ISBN: 92-0-111705-1
Publication Date: 15-12-2005
When selecting a proper decommissioning strategy in a specific facility, a range of general and site specific factors needs to be considered. These factors include cost, health and safety issues and environmental (HSE) impact, availability of resources, stakeholder involvement, etc. In some cases the lack of a single key resource could result in the elimination of some decommissioning strategies. Good practice may not always be achieved in Member States due to constraints or overruling factors such as a lack of funds or a lack of waste management infrastructure. Constraints or overruling factors are often attributable to inadequate decommissioning planning. This in turn may be due to inadequate legal and regulatory frameworks. Some relevant constraints and conditions have been evaluated. The objective of the evaluation is to identify key issues and to provide recommendations to Member States in which these constraints and factors prevail, to promote actions in support of good decommissioning practice.
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA-TECDOC-1479
ISBN: 92-0-111505-9
Publication Date: 12-12-2005
This publication is primarily intended for managers and specialists in nuclear facility operating organizations working in the area of human performance improvement. It is intended to provide them with practical information they can use to improve human performance in their organizations. While some of the information provided in this publication is based upon the experience of nuclear facility operating organizations, most of it comes from human performance improvement initiatives in non-nuclear organizations and industries. The nuclear industry has a long tradition of sharing good management practices in order to foster continuous improvement. However, it is not always realized that many of the practices that are now well established initially came from non-nuclear industries and were subsequently adapted for application to nuclear power plant operating organizations. There is, therefore, good reason to periodically review non-nuclear industry practices for ideas that might have direct or indirect application to the nuclear industry in order to potentially gain benefits such as the following: new approaches to certain problem areas, insights into new or impending challenges, improvements in existing practices, benchmarking of opportunities, development of learning organizations and avoidance of collective blind spots.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1481
ISBN: 92-0-113105-4
Publication Date: 19-12-2005
This report presents a brief overview of recent developments in evaluating the long term performance of selected human made materials (copper based metals, glasses and concrete). It summarizes the results of several studies which contribute to the information base on anthropogenic analogues. Although the primary intention was to promote development of an engineered system of geological repositories, some data are relevant to the performance of barriers considered when designing near surface disposal facilities. It is also expected that the published results may provide other workers in the field with an insight into the potential of the studied materials for their long term uses in constructions long term and for their exposure to extreme environmental conditions.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1482
ISBN: 92-0-112505-4
Publication Date: 15-12-2005
A particular challenge facing countries with small nuclear programmes is the preparation for extended interim storage and then disposal of their spent nuclear fuel. The costs and complications of providing for away-from-reactor storage facilities and/or geological repositories for relatively small amounts of spent fuel may be prohibitively high, motivating interest in regional solutions. This publication addresses the technical, economic and institutional aspects of regional spent fuel storage facilities and is based on the results of a series of meetings on this topic with participants from IAEA Member States.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1485
ISBN: 92-0-101006-0
Publication Date: 30-5-2006
The objective of this report is to provide Member States, including those considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, with balanced and objective information on important development trends and objectives of innovative small and medium sized reactors (SMRs) for a variety of uses, on the achieved state of the art in design and technology development for such reactors and on their design and regulatory status. The publication is intended for many categories of stakeholders, including regulators, electricity producers, designers, non-electricity producers and policy makers. The main sections of this publication, addressed to all the above mentioned groups of stakeholders, provide a summary of major specifications, applications and user related special features of innovative SMRs. The annexes, intended mainly for designers and technical managers, provide detailed design descriptions of innovative SMRs, focusing on their potential to provide solutions in the areas of concern associated with future nuclear energy systems.
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
IAEA-TECDOC-1487
ISBN: 92-0-100506-7
Publication Date: 21-3-2006
This report presents the state of the art in design approaches for the protection from external event impacts for nuclear power plants (NPPs) with evolutionary and innovative reactors. It provides both the general and the technical information background to assist designers of advanced NPPs in the definition of consistent strategies in selected issues of the design and siting evaluation in relation to extreme external events.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1490
ISBN: 92-0-102706-0
Publication Date: 30-5-2006
Planned outages are a main contributor to nuclear power plant (NPP) unavailability, risk and cost. Effective management of planned outages is a key factor for improvement of NPP safety, availability and competitiveness. To support outage management, an outage monitoring system is implemented that follows all the fundamental and critical activities and deadlines in each phase of the outage. The IAEA has produced this publication on indicators for planned outage monitoring as a complement to a series of technical publications related to practices regarding outage management and cost effective maintenance. The aim of this publication is to provide guidelines for outage monitoring systems, examples of specific outage indicators and good practices in outage monitoring. This publication outlines a set of outage indicators that could be considered by operators of NPPs when establishing or revising their own specific outage indicator systems.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1491
ISBN: 92-0-102906-3
Publication Date: 23-5-2006
In recent years there has been an upward trend in the safety and operational performance of nuclear installations. Continual improvement of the processes of organizations has led to enhanced safety performance and efficiency benefits such as cost reductions and improved cycle times. Many organizations have experienced significant cost improvement largely by or through better financial management. Without the use of a structured methodology to identify and implement improvements, changes to an organization to reduce costs through cutting staff and activities could eventually fail to produce the desired changes and even have a negative effect on safety and overall performance. The objectives of this publication are to explain how an approach to continual improvement can be implemented and how to conduct process improvements. It also describes good practices and the problems that may be encountered, based on experiences in a number of different organizations in the nuclear field. A number of case studies and a summary of some of the many improvement techniques available are provided. The methodology used in this publication contains steps and practices that are common to many of the continual improvement strategies. This publication will assist readers in successfully applying continual improvement in their own organizations in the pursuit of enhanced safety and improved performance.
Subject Classification: 0600 - Nuclear and Radiological Safety
IAEA-TECDOC-1492
ISBN: 92-0-103006-1
Publication Date: 30-5-2006
The focus of this report is on the low and intermediate level radioactive wastes generated and managed during the normal operating life of WWER nuclear power plants. It identifies mechanisms for reducing the generation and disposal volumes of radioactive waste at WWER reactors, and compares the waste management approaches of western PWR and WWER reactors to identify reasons why PWRs currently have lower waste generation, storage and disposal volumes. Examining historical trends in plant design and waste management approaches, it seeks to identify those changes which contribute most significantly to todays differences between PWRs and WWERs in generation and disposal volumes. The report determines the role of waste storage in promoting implementation of improved or advanced waste minimization technologies and approaches, and proposes recommendations for improving WWER waste minimization.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1496
ISBN: 92-0-104706-1
Publication Date: 7-8-2006
The thermophysical properties database for materials of light water reactors and heavy water reactors described in this technical document was established within the framework of an IAEA Coordinated Research Project. The database is intended to serve as a useful source of information on thermophysical properties data for water cooled reactor analyses. In particular, it aims at achieving improvements in safety and economics of future plants by helping to remove the need for large design margins to account for limitations of data and methods. The database has been developed into an internationally available Internet database (THERPRO) at Hanyang University (Republic of Korea), and now provides various materials properties data and an interactively accessible information resource and communications medium for researchers and engineers.
Subject Classification: 0306 - Nuclear data; 0703 - Reactor technology
IAEA-TECDOC-1499
ISBN: 92-0-105606-0
Publication Date: 4-8-2006
The IAEA has conducted a Coordinated Research Project (CRP) on Intercomparison of Techniques for HWR Pressure Tube Inspection and Diagnostics. This publication reports on the first phase of the CRP dealing with flaw characterization by in-situ non-destructive examination (NDE) techniques. The participating laboratories prepared pressure tube (PT) samples containing artificial hidden flaws resembling real defects of concern. All samples were then inspected from the inside surface, as in real conditions. The originating laboratories subsequently analysed the sample inspection reports from investigating laboratories and compared the NDE flaw sizing estimates with their true values. Thus, the most successful NDE methods for detection, location and sizing of various types of flaws in PTs were identified. This publication details how the research was conducted and documents results from the flaw detection and characterization activities.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1500
ISBN: 92-0-105706-7
Publication Date: 22-8-2006
The use of simulators for the training and qualification of control room operating personnel has become a standard practice throughout the world to develop and reinforce knowledge of plant systems and their relationships, to increase the ability to apply plant procedures, to advance practical skills in operating the plant in normal, abnormal and emergency conditions, and to build supervisory skills and teamwork. Simulators are also utilized to conduct the authorization or licensing examinations of control room operating personnel, and there is an increasing trend in the usage of simulators for non-training purposes. The simulator should be adequately maintained and upgraded to ensure that it continues to be a viable training tool that accurately replicates the operational characteristics of the reference nuclear power plant (NPP). The upgrade or modernization of the simulator should be conducted based upon the proven project management principles and methods discussed in this report. The combined simulator upgrade knowledge and experience of many NPPs and simulator vendors have been compiled, and examples of specific simulator upgrade projects are included in the appendices as well as on the attached CD-ROM.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1501
ISBN: 92-0-106106-4
Publication Date: 24-7-2006
This publication is devoted to human resource issues related to expanding a nuclear power plant (NPP) fleet, with particular emphasis on expansions including the use of new NPP designs. Lessons learned as well as information from NPP operating organizations in Member States are presented. It is intended that this publication be relevant for the full range of NPP technology considerations, up to and including Generation III innovative designs. The applicable expansion scenarios considered are: adding units of the same or very similar technology at existing sites, adding units of the same or very similar technology at new sites and adding units with considerably different technology (e.g., adding PWR units to a GCR fleet, adding an innovative plant design to an existing fleet).
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1502
ISBN: 92-0-105806-3
Publication Date: 5-9-2006
Authorization of control room personnel is a normal practice in all IAEA Member States operating nuclear power plants (NPPs). The authorization of personnel is based on whether personnel has a direct impact on safety in accordance with IAEA Safety Guide No. NS-G-2.8: Recruitment, Qualification and Training of Personnel for NPPs. The methods and practices for this authorization, however, are not identical, and the organization granting the authorization may be different. The various authorization processes are usually based on written and/or oral examinations and in many cases also on the testing of practical skills. Differences in the authorization processes also exist in the examination methodology and in the scope of the practical examinations (e.g., plant walkthrough, use of simulators). The recent increase in the availability of full-scope simulators, in particular full-scope plant-referenced control room simulators, provides an additional, efficient tool for testing the practical skills of the candidates for authorization. Information contained in this document and on the accompanying CD-ROM provides useful guidance and a wide range of practical examples that will be helpful for both NPP operating organizations and regulatory bodies in developing and improving the processes of authorization of control room personnel.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1503
ISBN: 92-0-106206-0
Publication Date: 17-8-2006
This publication provides an overview of the various plant life management (PLiM) methodologies, technologies and processes to ensure long term operation of heavy water reactors (HWRs). Implementation of a systematic and comprehensive PLiM programme, such as that outlined in the publication, goes a long way towards meeting the overall goal of HWR owners and operators to successfully achieve design life and continued operation. Included in this publication are technical aspects of HWR PLiM, component specific technology considerations for condition assessment, an example of a proactive ageing management programme, and Ontario power generation experiences. Country reports from Argentina, Canada, India, the Republic of Korea and Romania are attached in an annex in order to share practices and experiences of PLiM programmes.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1504
ISBN: 92-0-107706-8
Publication Date: 18-8-2006
Member States and individual nuclear power plants (NPPs) must carry out radioactive waste processing (treatment and conditioning) in an efficient and cost effective manner. Determination of which of the many available technologies and strategies are best suited to meet national or local needs is often a complex assessment. The aim of this publication is to inform decision makers by presenting information on innovative technologies for processing wastes generated by NPPs. The report identifies the key benefits which may derive from the adoption of those technologies, the different waste streams to which each technology is relevant, and the limitations of the technologies.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1505
ISBN: 92-0-107906-0
Publication Date: 2-10-2006
This publication provides information on the current status and development trends in monitoring, diagnostics and control of water chemistry and corrosion of core and primary circuit materials in water cooled power reactors. It summarizes the results of the IAEA Coordinated Research Project on Data Processing Technologies and Diagnostics for Water Chemistry and Corrosion Control in Nuclear Power Plants and focuses on the methods for development, qualification and implementation of water chemistry expert systems at nuclear power plants. The project had contributions from leading experts in water chemistry/corrosion, representing organizations from 16 countries with the largest nuclear capacities.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1508
ISBN: 92-0-109006-4
Publication Date: 1-9-2006
Research reactors operate in many IAEA Member States for radioisotope production, fundamental research in physics and biology, materials irradiation, education and training. This publication arises from an IAEA Technical Cooperation Regional Project developed by Latin American experts on research reactor spent fuel management. The publication describes technically feasible options available for management of spent fuel from research reactors in the participating Member States (Argentina, Brazil, Chile, Peru and Mexico) and these options are presented within the context of the economic considerations of the countries in question.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1509
ISBN: 92-0-108006-9
Publication Date: 4-8-2006
The increasingly competitive environment of the electricity sector has significant implications for nuclear power plant (NPP) operations. Management objectives must be focused on efficient operation as the key to profitability. The business and financial success of operating NPPs must be given greater consideration through an integrated approach which also ensures the successful achievement of safety and reliability objectives. In developing strategic and operational goals, nuclear plant managers will be required to embrace and articulate clear and measurable business objectives and goals which not only assure the achievement of safety and reliability but also eliminate unnecessary costs and identify investment opportunities. This publication looks at the optimization of the costs as an integrated part of the management of organization business process with a focus on planning (strategic and tactical) and on controlling (control system, corrective actions and pay reward) functions.
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-1510
ISBN: 92-0-108906-6
Publication Date: 20-11-2006
Managing knowledge in the nuclear industry will be one of the most critical challenges in the near future. The purpose of this publication is to identify the fundamental elements needed for an effective knowledge management (KM) system, to share with nuclear industry operating organization managers lessons learned regarding KM, as well as providing guidance concerning methods for KM implementation. Intended as an introduction to KM approaches and practices, this publication also provides guidance on improving KM practices in nuclear industry operating organizations. Senior and middle level managers of nuclear industry operating organizations will find that the book provides a wealth of practical information and is a critical resource informing their KM planning, system implementation and improvements.
Subject Classification: 0705 - Qualification and training of personnel
IAEA-TECDOC-1513
ISBN: 92-0-108506-0
Publication Date: 17-7-2006
There are several stages to the process of introducing nuclear power in a country. These include the development of nuclear policies and regulations, feasibility studies, public consultations, technology evaluation, request for proposals and proposal evaluation, project and contracts development and financing, supply, construction, and commissioning and finally operation. This publication addresses the "minimum" infrastructure requirements, which are adequate until the issue of the construction licence. The target readers are decision makers, advisers and senior managers in the governmental organizations, utilities, industrial organizations and regulatory bodies in the countries adopting nuclear power programmes or exporting supplies for these programmes.
Subject Classification: 0700 - Nuclear power
IAEA-TECDOC-1514
ISBN: 92-0-108806-X
Publication Date: 5-9-2006
This publication provides information for managers and executives of electrical utilities who are tasked with decision making related to early closure or continued operation of a nuclear power plant (NPP). The local or regional population, the customers for the electricity generated and those responsible for regional energy policy and the broader economic management of the region have different perceptions of the value of the NPP. The need for re-evaluations and any consequent project delays will depend on the perceived accountability of those making the decisions to the other stakeholders impacted by the decision, and the degree to which all relevant social, technical, environmental and economic issues are weighted in the decision making process. This publication provides information on several issues important to key stakeholders, and on methods that allow for their assessment and consideration when developing recommendations related to early closure or continued operation of an NPP.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1515
ISBN: 92-0-109206-7
Publication Date: 1-11-2006
The main objective of this publication is to provide guidelines for the development of waste package specifications that comply with waste acceptance requirements for storage and disposal of radioactive waste. It will assist waste generators and waste package producers in selecting the most significant parameters and in developing and implementing specifications for each individual type of waste and waste package. This publication also identifies and reviews the activities and technical provisions that are necessary to meet safety requirements; in particular, selection of the significant safety parameters and preparation of specifications for waste forms, waste containers and waste packages using proven approaches, methods and technologies. This report provides guidance using a systematic, step wise approach, integrating the technical, organizational and administrative factors that need to be considered at each step of planning and implementing waste package design, fabrication, approval, quality assurance and control. The report reflects the considerable experience and knowledge that has been accumulated in the Member States and is consistent with the current international requirements, principles, standards and guidance for the safe management of radioactive waste.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1516
ISBN: 92-0-110506-1
Publication Date: 26-9-2006
Reactors worldwide have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post-irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Subject Classification: 0803 - Spent fuel management; 0803 - Spent fuel management
IAEA-TECDOC-1518
ISBN: 92-0-111106-1
Publication Date: 2-10-2006
Some radioactive wastes arising at nuclear facilities have been stored for an extended period of time, often beyond the expected life time of the storage vessels. IAEA Member States are moving forward with actions to retrieve such wastes for safe disposition. This document covers the development of waste retrieval systems, with a specific focus on the safe removal and transfer of wastes which are in fluid form or which can be mobilized as wet or dry media. Detailed discussions are included on retrieval methodology, technologies and approaches. Extensive examples are provided for 21 waste retrieval projects completed or currently under way around the world, including lessons learned.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1519
ISBN: 92-0-111706-X
Publication Date: 14-2-2007
Data collection and maintenance are an essential part of activities required in the lifetime management of spent fuel. Key data on spent fuel are required from the earliest phase of any project. To allow informed decisions for spent fuel management to be made, the data need to be maintained throughout the lifetime of spent fuel management including storage, transport, reprocessing or disposal. This publication is intended to provide a state-of-the-art review of spent fuel data management, including what data need to be gathered for the relevant activities in spent fuel management and how to maintain them by the responsible bodies at various stages of the nuclear fuel cycle.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1520
ISBN: 92-0-111806-6
Publication Date: 6-12-2006
The experience in heavy liquid metal (HLM) thermal fluid dynamics with regard to both the theoretical or numerical and experimental fields is limited, and somewhat dispersed. Examples would be turbulent exchange phenomena, free-surface problems, and two-phase flows. This publication performs an assessment of the shortcomings of the present computational fluid dynamics codes used for HLM simulation and identifies future research activities, in both the numerical and experimental areas, to address these shortcomings.
Subject Classification: 0703 - Reactor technology; 0703 - Reactor technology
IAEA-TECDOC-1521
ISBN: 92-0-112006-0
Publication Date: 1-11-2006
Dismantling and management of radioactive graphite and carbon, which is used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium production reactors, presents significant technological and safety challenges. The large quantities of radioactive graphite waste generated (over 200 000 t worldwide) and the specific properties of graphite demonstrate a need for complex planning and implementation of several interrelated operations. This document provides decision makers, nuclear facility managers and engineers, waste managers and other involved bodies with comprehensive, technologically oriented information on the present state and the recent achievements in radioactive graphite waste management. It is applicable to the planning and development of decommissioning procedures, processing of radioactive graphite waste and processing for final disposal.
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1522
ISBN: 92-0-112106-7
Publication Date: 17-11-2006
The introduction or expansion of a nuclear power programme in a country and its successful execution are largely dependent on the network of national infrastructure, covering a wide range of organizational and material activities and capabilities. The wide extent of infrastructure needs requires an investment that could be large or onerous for the national economy. The burden of infrastructure can be reduced significantly if a country forms a sharing partnership with other countries. The sharing could be organized regionally or internationally. It can include physical facilities, common programmes and knowledge, and will reflect in economic benefits. This publication provides guidance for analysing and identifying the potential benefits of sharing nuclear power infrastructure during various stages of the nuclear power project life cycle. The target users of this publication are decision makers, advisers and senior managers in utilities, industrial organizations, regulatory bodies and governmental organizations in countries adopting or extending nuclear power programmes.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-1523
ISBN: 92-0-112706-5
Publication Date: 12-3-2007
As delays are incurred in implementing reprocessing and in planning for geological repositories, storage of increasing quantities of spent fuel for extended durations is becoming a reality. Accordingly, effective management of spent fuel continues to be a priority topic within the IAEA and its Member States. As an example, cask designers face evolving challenges including long term storage of higher burnup fuel with correspondingly higher initial enrichments, the use of mixed oxide (MOX) fuel, and obtaining regulatory approval for the use of burnup credit. As a result, the IAEA has organized a series of meetings to identify cask loading optimization issues in preparation for a technical report on Optimization of Cask/Container Loading for Long Term Spent Fuel Storage. This publication outlines the optimization process for cask design, licensing and utilization, describing three principal groups of optimization activities in terms of relevant technical considerations (e.g. criticality, thermal, shielding, structural design, operations, maintenance, retrievability).
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1524
ISBN: 92-0-112806-1
Publication Date: 7-3-2007
This Status Report briefly describes the recent nuclear seawater desalination related developments in IAEA Member States and relevant IAEA activities. It covers salient aspects of the new generation reactors and some innovative reactors being considered for desalination, recent advances in commonly employed desalination processes and their coupling to nuclear reactors. A summary of the techno-economic feasibility studies carried out in interested Member States is presented. The socioeconomic and environmental benefits of nuclear power driven desalination plants are discussed.
Subject Classification: 0500 - Industrial Applications
IAEA-TECDOC-1527
ISBN: 92-0-113806-7
Publication Date: 14-2-2007
The primary objective of this publication is to provide an overview of the various thermal technologies for processing various solid, liquid, organic and inorganic radioactive waste streams. The advantages, limitations and operating experience of various thermal technologies are explained. This publication also goes beyond previous work on thermal processes by addressing the applicability of each technology to national or regional nuclear programmes of specific relative size (major advanced programmes, small to medium programmes, and emerging programmes with other nuclear applications).
Subject Classification: 0804 - Waste management
IAEA-TECDOC-1531
ISBN: 92-0-114206-4
Publication Date: 20-2-2007
The fast reactor database (FRDB) summarized in this report is very detailed with each liquid metal cooled fast reactor (LMFR) power plant being characterized by about 500 items. It includes operational parameters, physical, hydraulic and thermomechanical characteristics, technological requirements and methods and criteria to ensure safe operation. It also covers design data such as dimensions, materials information and main design features and performance parameters of reactor cores, components and various systems, along with sketches and drawings. The database setup makes it possible not only to easily find the required parameter of a certain reactor, but also to compare it with that of the other reactors. The FRDB includes data on 37 fast reactor plants, their thermal power ranging from 10 to 4000 MW. Thirty-one reactors out of 37 are connected to steam turbine generators of 12 to 1800 MW electric power. It is hoped that this reference book will allow effective design approaches for fast reactor systems and components to be reproduced and the repetition of unsuccessful design approaches to be avoided.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-1532
ISBN: 92-0-115006-7
Publication Date: 12-3-2007
Member States have a growing need for casks for spent fuel storage and transportation. A variety of casks has been developed and is in use at an increasing number of sites. This has resulted in an accumulation of experience that will provide valuable information for other projects in spent fuel management. This publication provides a comprehensive review of information on the cask operation and maintenance associated with spent fuel storage. It draws upon generic knowledge from industrial experience and applications and is intended to serve as a basis for better planning and implementation in future projects.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-1541
ISBN: 92-0-101107-5
Publication Date: 15-3-2007
The Baltic States are in the process of reorganization, moving from a centrally planned economy towards market liberalization. The closure of Unit 1 of the Ignalina Nuclear Power Plant in 2004 and the scheduled shutdown of Unit 2 in 2009 in accordance with the EU accession agreement raise crucial supply security questions not only for Lithuania but for the region as a whole. This study provided the opportunity to analyse the economic competitiveness and energy security aspects of a wide range of energy supply options including the construction of a new nuclear power plant.
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-CD-1318
ISBN: 92-0-109903-7
Publication Date: 1-9-2003
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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-CD-1320
ISBN: 92-0-134702-2
Publication Date: 2-12-2002
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-CD-1345
ISBN: 92-0-102203-4
Publication Date: 16-4-2003
The report on CD-ROM 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.
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-CD-1363
ISBN: 92-0-109503-1
Publication Date: 11-11-2003
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.
IAEA-TECDOC-CD-1378
ISBN: 92-0-111303-X
Publication Date: 16-12-2003
IAEA-TECDOC-CD-1385
ISBN: 92-0-109604-6
Publication Date: 24-8-2004
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 Tecdoc. 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 TECDOC contains the results of pre-characterization of the rods, descriptions of the tests and the results of characterizations in the two principal temperature regimes.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-CD-1391
ISBN: 92-0-109704-2
Publication Date: 24-8-2004
The report is intended to be a source of reference information for interested organizations and individuals. Among them are decision makers of countries considering implementation of nuclear power programmes. Further, 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 on the global status 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.
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-CD-1433
ISBN: 92-0-103605-1
Publication Date: 3-6-2005
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-CD-1467
ISBN: 92-0-111405-2
Publication Date: 5-10-2005
The management of spent fuel arising from nuclear power production is a crucial issue for the sustainable development of nuclear energy. The IAEA has issued several publications in the past that provide technical information on the global status and trends in spent fuel reprocessing and associated topics, and one reason for this present publication is to provide an update of this information which has mostly focused on the conventional technology applied to industry. However, the scope of this publication has been significantly expanded in an attempt to make it more comprehensive and by including a section on emerging technologies applicable to future innovative nuclear systems, as are being addressed in such international initiatives as INPRO, Gen IV and MICANET. In an effort to be informative, this publication attempts to provide a state-of-the-art review of the technologies, and to identify major issues associated with reprocessing as an option for spent fuel management. It does not, however, provide any detailed information on some of the related issues, such as safety or safeguards, which are addressed in other relevant publications.
IAEA-TECDOC-CD-1482
ISBN: 92-0-114605-1
Publication Date: 4-1-2006
A particular challenge facing countries with small nuclear programmes is the preparation for extended interim storage and then disposal of their spent nuclear fuel. The costs and complications of providing for away-from-reactor storage facilities and/or geological repositories for relatively small amounts of spent fuel may be prohibitively high, motivating interest in regional solutions. This publication addresses the technical, economic and institutional aspects of regional spent fuel storage facilities and is based on the results of a series of meetings on this topic with participants from IAEA Member States.
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-CD-1485
ISBN: 92-0-101106-7
Publication Date: 31-5-2006
The objective of this report is to provide Member States, including those considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, with balanced and objective information on important development trends and objectives of innovative small and medium sized reactors (SMRs) for a variety of uses, on the achieved state of the art in design and technology development for such reactors and on their design and regulatory status. The publication is intended for many categories of stakeholders, including regulators, electricity producers, designers, non-electricity producers and policy makers. The main sections of this publication, addressed to all the above mentioned groups of stakeholders, provide a summary of major specifications, applications and user related special features of innovative SMRs. The annexes, intended mainly for designers and technical managers, provide detailed design descriptions of innovative SMRs, focusing on their potential to provide solutions in the areas of concern associated with future nuclear energy systems.
IAEA-TECDOC-CD-1519
ISBN: 92-0-101007-9
Publication Date: 7-3-2007
Data collection and maintenance are an essential part of activities required in the lifetime management of spent fuel. Key data on spent fuel are required from the earliest phase of any project. To allow informed decisions for spent fuel management to be made, the data need to be maintained throughout the lifetime of spent fuel management including storage, transport, reprocessing or disposal. This publication is intended to provide a state-of-the-art review of spent fuel data management, including what data need to be gathered for the relevant activities in spent fuel management and how to maintain them by the responsible bodies at various stages of the nuclear fuel cycle.
IAEA-TECDOC-CD-1520
ISBN: 92-0-101907-6
Publication Date: 12-3-2007
The experience in heavy liquid metal (HLM) thermal fluid dynamics with regard to both the theoretical or numerical and experimental fields is limited, and somewhat dispersed. Examples would be turbulent exchange phenomena, free-surface problems, and two-phase flows. This publication performs an assessment of the shortcomings of the present computational fluid dynamics codes used for HLM simulation and identifies future research activities, in both the numerical and experimental areas, to address these shortcomings.
IAEA-TECDOC-CD-1523
ISBN: 92-0-102907-1
Publication Date: 12-3-2007
As delays are incurred in implementing reprocessing and in planning for geological repositories, storage of increasing quantities of spent fuel for extended durations is becoming a reality. Accordingly, effective management of spent fuel continues to be a priority topic within the IAEA and its Member States. As an example, cask designers face evolving challenges including long term storage of higher burnup fuel with correspondingly higher initial enrichments, the use of mixed oxide (MOX) fuel, and obtaining regulatory approval for the use of burnup credit. As a result, the IAEA has organized a series of meetings to identify cask loading optimization issues in preparation for a technical report on Optimization of Cask/Container Loading for Long Term Spent Fuel Storage. This publication outlines the optimization process for cask design, licensing and utilization, describing three principal groups of optimization activities in terms of relevant technical considerations (e.g. criticality, thermal, shielding, structural design, operations, maintenance, retrievability).
IAEA/CMS/18
Publication Date: 15-2-2006
MAED evaluates future energy demands based on medium to long term scenarios of socioeconomic, technological and demographic development. Energy demand is disaggregated into a large number of end-use categories corresponding to different goods and services. The influences of social, economic and technological driving factors from a given scenario are estimated. These are combined to give an overall picture of future energy demand growth. The IAEA provides training on the use of this model to local professionals upon request from interested Member States. MAED has already been distributed to over 60 Member States.
Subject Classification: 9999 - All fields
IAEA/CMS/19
Publication Date: 13-4-2006
IAEA/CMS/20
Publication Date: 7-3-2007
IAEA/FCW/NL/01/01
Publication Date: 14-9-2005
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA/FCW/NL/01/02
Publication Date: 21-12-2005
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA/FCW/NL/02/01
Publication Date: 23-5-2006
Subject Classification: 0800 - Nuclear fuel cycle and waste management
IAEA/NI/KM/NL/01
Publication Date: 27-4-2006
Subject Classification: 1200 - International Nuclear Information System
IAEA/NI/KM/NL/02
Publication Date: 5-9-2006
Subject Classification: 1200 - International Nuclear Information System
IAEA/NP/NL/01/01
Publication Date: 21-9-2004
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/01/02
Publication Date: 3-12-2004
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/02/01
Publication Date: 21-2-2005
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/02/02
Publication Date: 14-6-2005
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/02/03
Publication Date: 13-9-2005
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/02/04
Publication Date: 16-1-2006
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/03/01
Publication Date: 12-4-2006
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/03/02
Publication Date: 10-7-2006
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/03/03
Publication Date: 5-9-2006
Subject Classification: 0700 - Nuclear power
IAEA/NP/NL/03/04
Publication Date: 22-1-2007
Subject Classification: 0700 - Nuclear power
IAEA/NPES/NL/04/01
Publication Date: 27-2-2003
Subject Classification: 0700 - Nuclear power
IAEA/WMDB/6
Publication Date: 16-3-2005
Subject Classification: 0611 - Radioactive waste management
IAEA/WMDB/ST/4
Publication Date: 22-4-2005
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
IAEA/WMRA/27/CD
Publication Date: 29-10-2002
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management; 0804 - Waste management
IAEA/WMRA/28/CD
Publication Date: 24-12-2003
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management; 0804 - Waste management
IAEA/WMRA/29/CD
Publication Date: 1-12-2004
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management; 0804 - Waste management
INDAG/NL/04
Publication Date: 21-9-2004
Subject Classification: 0702 - Nuclear power operations
STI/DOC/010/406
ISBN: 92-0-110202-X
Publication Date: 18-3-2002
This report discusses the means and principal issues for the development of a nuclear economic performance international system, with the purpose of enhancing nuclear power plant competitiveness. It addresses the major transformations occurring in the electricity generation industry to achieve operation and maintenance (O&M) cost reductions and is therefore primarily intended for nuclear power plant and utility managers. The report further presents the preliminary results of a pilot project showing a collection of cost data on a few nuclear power plants, which was used to verify the adequacy of the definitions and terminology set. Contents: 1. Introduction; 2. Transformations causing utilities to optimize O&M costs; 3. Applicability of a nuclear economic performance international system; 4. Establishing a nuclear economic performance international system (NEPIS); 5. Conclusions; Annex I: Using frontier analysis to optimize costs and performance; Annex II: Monetary conversion tables; Annex III: Definitions and terminology for NEPIS; Annex IV: Glossary of business terms; Annex V: IAEA power reactor information system definitions.
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/407
ISBN: 92-0-111502-4
Publication Date: 17-5-2002
This report outlines the characteristics of heavy water reactors and provides an insight into the technology for specialists in countries where the establishment of nuclear power programmes is being considered. It should serve as a reference for engineers and scientists working in the field, as well as for lecturers in nuclear technology. Contents: Section 1. Introduction; Section 2. HWR evolution; Section 3. Characteristics of HWRs; Section 4. Economics of HWRs; Section 5. Safety aspects of HWRs; Section 6. HWR fuel cycles; Section 7. Environmental considerations; Section 8. Vision of advanced HWR designs; Appendix: Parameters of the principal types of HWR.
Subject Classification: 0703 - Reactor technology; 1300 - Environment
STI/DOC/010/408
ISBN: 92-0-112002-8
Publication Date: 22-7-2002
Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. Various aspects of ion exchange technology are being actively studied in many countries to improve efficiency and economy. Spent ion exchangers are considered to be problematic waste that in many cases requires special approaches and precautions during its immobilization to meet the acceptance criteria for disposal. This books reviews and updates the current literature on the subject and reports on the existing state of the art of the application of ion exchange processes for liquid radioactive waste treatments and of the management of spent ion exchange media.
Subject Classification: 0611 - Radioactive waste management; 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/410
ISBN: 92-0-115402-X
Publication Date: 2-4-2003
Nuclear energy has a much wider potential than being used solely for the generation of electricity. This publication concentrates on the market potential and economics of the nuclear option in district heating, the supply of process heat, water desalination, ship propulsion and outer space applications. In addition, there is an overview of innovative but promising areas for its use, such as fuel synthesis (including hydrogen production) and oil extraction.
Subject Classification: 0300 - Nuclear Measurements, Techniques and Instrumentation; 0500 - Industrial Applications
STI/DOC/010/411
ISBN: 92-0-119602-4
Publication Date: 11-3-2003
The objective of this report is to provide information, based on experience gained so far, on how to identify, maintain and update the necessary records for the decommissioning of nuclear facilities. Record keeping has proven to be of vital importance, since its lack may result in the costly misallocation of resources and may cause safety problems. Contents: 1. Introduction; 2. Scope and objectives; 3. Design and operational data requirements for decommissioning; 4. Process of selecting decommissioning records; 5. Retention of decommissioning records; 6. Quality assurance; 7. The records management system; 8. Management of new records; 9. Summary; Appendix: Options for record storage media and retrievability; Annex I: Examples of national experience; Annex II: Lessons learned.
Subject Classification: 0611 - Radioactive waste management; 0702 - Nuclear power operations; 0804 - Waste management
STI/DOC/010/412
ISBN: 92-0-118702-5
Publication Date: 6-1-2003
This comprehensive report discusses, in a generic sense, the scientific and technical basis for the disposal of low and intermediate level waste in near surface repositories. It is based on the experience of Member States with operational disposal facilities and on relevant national and international research and development studies. It focuses on basic principles, approaches, methodologies and technical criteria considered to be important for the design and safe operation of a near surface disposal facility, and for providing a convincing safety case that also covers the periods following repository closure and the end of institutional controls. Contents: 1. Introduction; 2. Near surface disposal concepts; 3. Near field; 4. Far field; 5. Biosphere; 6. Confidence in repository performance and safety; 7. Summary and conclusions.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/413
ISBN: 92-0-100103-7
Publication Date: 27-2-2003
This report focuses on the different functions of a repository within its life cycle and describes the processes relevant to the containment of long lived radioactive waste and other criteria influencing the long term integrity of the repository. It emphasizes the central role of safety and the importance of safety/performance assessments in the decision making process during repository development. Contents: 1. Introduction; 2. The geological disposal concept; 3. Near field components and processes; 4. Far field barriers and processes; 5. Confidence in adequate isolation; 6. Summary and conclusions.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/414
ISBN: 92-0-101003-6
Publication Date: 16-5-2003
This publication proves information, experience and assistance on the decommissioning of small medical, industrial and research nuclear facilities in which radioactive material and radiation sources are produced, received, used and/or stored. This report is intended to promote timely and cost effective decommissioning and waste management at the end of the life of a small facility so as to render such a facility harmless.
Subject Classification: 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/415
ISBN: 92-0-103103-3
Publication Date: 4-6-2003
This report gives an overview of the worldwide state of plutonium fuel development with an outline of future trends. The review was prepared by a group of experts in the field and supported by information from specialists in plutonium fuel developments and related subjects. Information on the present status of, and development trends in, MOX fuel technology in the areas of design, fabrication, performance, in-core fuel management, transportation, spent MOX fuel management, decommissioning, waste treatment, safeguards and alternative approaches for plutonium recycling is provided. The report concentrates on MOX fuel for thermal power reactors; however, specific aspects of fast reactor MOX fuel are also considered.
Subject Classification: 0602 - Fuel fabrication and storage; 0702 - Nuclear power operations; 0802 - Fuel fabrication and performance
STI/DOC/010/417
ISBN: 92-0-106103-X
Publication Date: 26-8-2003
This report presents an integrated, stepwise approach for the development of near surface disposal facilities for low and intermediate level radiactive waste. The report is consistent with the current international requirements, principles, standards and guidance for the disposal of radioactive waste. The approach is designed to be flexible enough to be suitable for use in the various Member States, ranging from countries that have nuclear power plants to countries that have small inventories of radioactive waste from nuclear applications.
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
STI/DOC/010/418
ISBN: 92-0-113703-6
Publication Date: 5-1-2004
This report describes research performed in ten laboratories within the framework of the IAEA Co-ordinated Research Project on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water. The project consisted of exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and the evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water. A group of experts in the field contributed a state-of-the-art review and provided technical supervision of the project. Localized corrosion mechanisms are notoriously difficult to understand, and it was clear from the outset that obtaining consistency in the results and their interpretation from laboratory to laboratory would depend on the development of an excellent set of experimental protocols. These experimental protocols are described in the report together with guidelines for the maintenance of optimum water chemistry to minimize the corrosion of aluminium clad research reactor fuel in wet storage.
Subject Classification: 0602 - Fuel fabrication and storage; 0702 - Nuclear power operations; 0802 - Fuel fabrication and performance
STI/DOC/010/419
ISBN: 92-0-112503-8
Publication Date: 9-1-2004
The purpose of this report is to raise awareness of the residues arising from the processing of various naturally occurring radioactive materials and the possible environmental contamination arising from these. The various processes and their residues are analysed and the technical options for dealing with such contamination are discussed. The industries of interest include those related to fuel production, water use, metal ores and industrial minerals.
Subject Classification: 0609 - Radiation protection; 0804 - Waste management
STI/DOC/010/420
ISBN: 92-0-114103-3
Publication Date: 14-6-2004
The transition period between operation of an installation and the implementation of the decommissioning strategy is a critical one. In this period, a number of modifications, both technical and organizational, are needed to adjust a plant to meet new objectives and requirements. It is essential that detailed planning for decommissioning begin in good time during plant operation and that preparatory actions for the implementation of the decommissioning strategy be initiated immediately after permanent shutdown. This ensures a gradual transition and minimizes uncontrolled loss of resources. The purpose of this report is to highlight technical, management and organizational issues during the transition period, to provide guidance to minimize delays and undue costs, to optimize personnel and other resources, and to initiate preparatory activities for decommissioning in a planned, timely and cost effective manner.
Subject Classification: 0611 - Radioactive waste management; 0701 - Nuclear power planning and economics; 0804 - Waste management
STI/DOC/010/421
ISBN: 92-0-114303-6
Publication Date: 15-9-2004
This report reviews and analyses experience in the application of different organizational and technological approaches to the management of waste containing C-14 and tritium, and reviews the different sources of such waste and the characteristics important in the selection of appropriate methods for its processing, storage, disposal and release.
Subject Classification: 0611 - Radioactive waste management; 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/424
ISBN: 92-0-114603-5
Publication Date: 4-2-2005
This report provides an overview of remediation technologies that are particularly suited to the remediation of dispersed contamination. Dispersed low level contamination poses a particular challenge. Many techniques are not efficient below certain concentration thresholds or entail more severe impacts on certain environmental compartments than the contamination itself. The technologies are outlined in brief, and their advantages and limitations are discussed. The need for a holistic design of the remedial action is stressed.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/425
ISBN: 92-0-114803-8
Publication Date: 24-11-2005
In recent years, activities related to the nuclear fuel cycle have expanded globally. In addition, the complexity of the nuclear fuel cycle market has increased with the emergence of new providers of fuel cycle services. In this context, a need was perceived for a compilation of country profiles on nuclear fuel cycle activities in a form which could be easily understood both by experts and by the public, and which should lead to a greater understanding of these activities worldwide. Furthermore, such information would improve the transparency of nuclear energy development in general. The second edition represents the status of the nuclear fuel cycle at the end of 2002 and consists of two parts: the first part is a review of worldwide activities related to the nuclear fuel cycle; the second comprises the country profiles, reflecting each countrys status with regard to nuclear fuel cycle activities. The second part incorporates a graphical representation of material flow in the nuclear fuel cycle of each country.
Subject Classification: 0800 - Nuclear fuel cycle and waste management
STI/DOC/010/427
ISBN: 92-0-103204-8
Publication Date: 20-8-2004
A wide variety of organic radioactive waste is generated at different nuclear fuel cycle facilities, as well as during different nuclear applications including medicine, research, agriculture, industry, education and training. Processing of organic waste for storage and disposal requires specific approaches. In many cases application of special techniques to destroy organic components of waste or to provide reliable immobilization to isolate organic waste from the environment is required. The processing of organic waste is a rapidly developing field. Various treatment and conditioning options are being investigated, developed and widely applied in several IAEA Member States. This report revises and summarizes available information on different treatment and conditioning options applied for predisposal management of organic radioactive waste.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/428
ISBN: 92-0-104704-5
Publication Date: 15-6-2005
The IAEAs Power Reactor Information System (PRIS) contains detailed information on nuclear power plants worldwide since they started commercial operation. It covers a broad range of information, including reactor design characteristics, plant general specifications, operating experience data and non-electrical applications of nuclear power plants such as steam production and desalination. This report describes all the elements of PRIS and explains the rules, coding, terminology and definitions used in the system.
Subject Classification: 0603 - Nuclear power plants; 0701 - Nuclear power planning and economics; 0702 - Nuclear power operations
STI/DOC/010/429
ISBN: 92-0-112104-0
Publication Date: 22-4-2005
The master curve approach for assessing the fracture toughness of a sampled irradiated material has been gaining acceptance around the world. This direct measurement approach is preferred over the correlative and indirect methods used in the past to assess irradiated reactor pressure vessel (RPV) integrity. The master curve methodology already has been or is being assimilated into the ASME Boiler and Pressure Vessel Code, ASTM standards, USNRC regulations, German regulations (KTA 3203) and IAEA PTS guidelines for WWER reactors, as well as the VERLIFE Unified Procedure for WWER Component Lifetime Assessment and other industry guidance documents governing RPV integrity analysis. As this report was prepared using the results of many research projects and experiments, these guidelines for application will be used for a long time to evaluate and assess the residual life of RPVs.
Subject Classification: 0702 - Nuclear power operations
STI/DOC/010/431
ISBN: 92-0-106804-2
Publication Date: 10-3-2005
Membrane separation processes have made impressive progress since the first synthesis of membranes almost 40 years ago. This progress was driven by strong technological needs and commercial expectations. As a result the range of successful applications of membranes and membrane processes is continuously broadening. In addition, increasing application of membrane processes and technologies lies in the increasing variations of the nature and characteristics of commercial membranes and membrane apparatus. The objective of the report is to review the information on application of membrane technologies in the processing of liquid radioactive waste. The report covers the various types of membranes, equipment design, range of applications, operational experience and the performance characteristics of different membrane processes. The report aims to provide Member States with basic information on the applicability and limitations of membrane separation technologies for processing liquid radioactive waste streams.
Subject Classification: 0804 - Waste management
STI/DOC/010/433
ISBN: 92-0-112704-9
Publication Date: 13-10-2005
This report considers a variety of circumstances that may require corrective actions to be assessed or implemented at near surface disposal facilities. The circumstances leading to the corrective actions, or the corrective actions themselves, may be of either a technical or a non-technical nature. Methodologies that can be employed to implement effective solutions to problems are discussed, including assessment of alternative options prior to selecting corrective actions, and the planning, implementation and verification of the specific measures adopted. Examples are provided of approaches and technologies that may be used to improve repository performance and safety. Information is also provided in the Annex on experience in various Member States with the upgrading of disposal facilities.
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
STI/DOC/010/434
ISBN: 92-0-114704-X
Publication Date: 17-3-2005
During processing, radioactive waste is converted into waste packages and sent for storage and ultimately for disposal. A principal condition for acceptance of a waste package for storage or disposal is its full compliance with waste acceptance criteria for disposal or storage. To declare compliance of a waste package with waste acceptance criteria, a system for generating and maintaining records should be established to record and track all relevant information, from raw waste characteristics, through changes related to waste processing, up to final checking and verification of waste package parameters. Records generated during waste processing are a constituent part of the more complex system of waste management record keeping, covering the entire life cycle of radioactive waste from generation to disposal and even the post-closure period of a disposal facility. The IAEA is systematically working on the preparation of a set of publications to assist its Member States in the development and implementation of such a system. This report covers all the principal aspects of the establishment and maintenance of records during waste processing and storage.
Subject Classification: 0804 - Waste management
STI/DOC/010/435
ISBN: 92-0-115104-7
Publication Date: 8-3-2005
Partitioning and transmutation (P&T) is a potential complementary route in the management of spent fuel resulting from the generation of nuclear power. It has the potential to open new avenues for long term waste management by eliminating long term radionuclides and their thermal effects and thus reducing the necessity or capacities of disposal facilities. Recycling and reuse of nuclear material and other transuranic radioisotopes would have positive effects on the sustainability of nuclear energy and reduce proliferation concerns by burning nuclear material and other transuranic radionuclides. This report analyses, from an international perspective, the current status of P&T, the potential options for its implementation and its impact on waste management programmes and strategies.
Subject Classification: 0804 - Waste management
STI/DOC/010/436
ISBN: 92-0-100305-6
Publication Date: 1-9-2005
This report presents a review of relevant information on the various technical factors and issues, as well as approaches and relevant technologies, leading to the identification of potential disposal options for disused radioactive sources. The report attempts to provide a logical 'road map' for the disposal of disused radioactive sources, taking into consideration the high degree of variability in the radiological properties of such types of radioactive waste. The use of borehole or shaft type repositories is highlighted as a potential disposal option, particularly for those countries that have limited resources and are looking for a simple, safe and cost effective solution for the disposal of their radioactive source inventories. The information provided in the report could be adapted or adopted to identify and develop specific disposal options suitable for the type and inventory of radioactive sources kept in storage in a given Member State.
Subject Classification: 0605 - Radiation sources and accelerators; 0804 - Waste management
STI/DOC/010/437
ISBN: 92-0-100905-4
Publication Date: 27-4-2006
This report has been prepared for the benefit of nuclear plant managers and operators. Its primary purpose is to identify and define a number of economic performance measures for use at nuclear power plants operating in deregulated, competitive electricity markets. In addressing the value of economic measures, the report presents and discusses a general definition and classifications of nuclear economic indicators within the context of regulation, competition and the economic requirements for constructing, operating and decommissioning nuclear plants.
Subject Classification: 0603 - Nuclear power plants; 0701 - Nuclear power planning and economics
STI/DOC/010/439
ISBN: 92-0-104405-4
Publication Date: 18-5-2006
Among the facilities requiring decommissioning are underground facilities. These require special consideration and are the subject of this publication. Firstly, due to their poor accessibility, there are significant difficulties in physical and radiological characterization, deployment of decontamination techniques, and physical disassembly and removal. Secondly, these types of components are present in a large number of nuclear installations. However, early nuclear design and construction practices often did not consider or incorporate eventual decommissioning requirements in their design considerations and these requirements were not commonly enforced in the early nuclear era. This is also true for those facilities situated in countries that do not have sufficient experience/expertise in performing decommissioning. Thirdly, a comprehensive assessment of the literature on nuclear decommissioning of underground components shows that this subject has not yet received any systematic coverage, despite the technical difficulties that have been encountered in actual projects to date. In fact, the literature on this subject is comprised of rather sporadic case histories. This publication is intended to draw attention to a neglected field and to collate/condense sporadic information into an overview of important factors and practical guidance.
Subject Classification: 0804 - Waste management
STI/DOC/010/440
ISBN: 92-0-104505-0
Publication Date: 19-12-2005
Nearly all nuclear installations utilize stacks to discharge ventilation air as well as gases and fumes from contaminated areas. Over a service lifetime that can span decades, stacks may become contaminated as the result of deposition of radioactive substances, such as aerosols on stack surfaces. In the longer term, this is a serious decommissioning issue. This contamination may be difficult to remove, depending on the operating conditions and the chemicalphysical environments over time. In addition, the physical logistics of stack dismantling may be complex, for example the difficulty in severing concrete high above the ground. Relevant aspects include project planning and management, decontamination and dismantling, and the management and disposal of wastes. Although more than 40 previous IAEA reports have been published in the field of decommissioning, none focus on this subject. It can be assumed that generic decontamination and dismantling technologies would also apply to these bulky components, but such an approach disregards a number of specific physical and radiological characteristics that make stack decommissioning a unique project.
Subject Classification: 0804 - Waste management
STI/DOC/010/441
ISBN: 92-0-104605-7
Publication Date: 23-1-2006
Decommissioning of old nuclear facilities may introduce several problems associated with management of some specific materials and waste with not only a radioactive nature but also with chemical toxicity, other dangerous properties or complicated characteristics. Materials such as asbestos, beryllium, cadmium, mercury, lead and PCBs could be considered, which were widely used in the past in the construction of facilities. This report describes several specific forms of materials and waste generated during decommissioning of old nuclear facilities, and outlines the management options for such waste and materials, which are different from those for waste generated during the facilitys normal operation.
Subject Classification: 0804 - Waste management
STI/DOC/010/442
ISBN: 92-0-104705-3
Publication Date: 6-3-2006
The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the management of the legacies of past practices and accidents. In response to this, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation. Mixed radioactive and hazardous substances contamination poses a particular challenge because of the combination of types of hazards and potential exposures. While radionuclides and toxic (heavy) metals pose similar and mostly compatible challenges, organic contaminants often require different approaches that may not be compatible with the former. Additional complexity is introduced into the problem by a different and sometimes conflicting regulatory framework for radiological and non-radiological contamination, including the prescribed waste management routes. In consideration of the added complexities of remediating mixed contamination, the IAEA published this.
Subject Classification: 0804 - Waste management
STI/DOC/010/443
ISBN: 92-0-105205-7
Publication Date: 7-6-2006
This report results from a Coordinated Research Project on Ageing of Materials in Spent Fuel Storage Facilities. It includes sections on the status of understanding ageing of selected materials and on management of ageing. The management of ageing is of key importance in many countries for the owners and operators of many facilities, including power reactors. There is a large measure of agreement on the general approach, which is summarized in this report. The report also includes a brief section on specific approaches in the context of fuel storage facilities and some specific recommendations. Moreover, the content has been broadened to try to appeal to those who may be in the early stages of setting up ageing management programmes either for new or for older fuel storage facilities. The report differentiates between the ageing of fuel materials from research reactors and civil reactors.
Subject Classification: 0803 - Spent fuel management
STI/DOC/010/444
ISBN: 92-0-105505-6
Publication Date: 31-5-2006
In the coming decades a large number of nuclear facilities will reach the end of their useful lives and require decommissioning. Many of these facilities will be decommissioned with the aim of either replacing them with new facilities that serve the same purpose or reusing the site for another, completely different purpose. By recognizing and promoting the redevelopment potential of facilities and their sites at the design stage or earlier in their operating life, it is possible to enhance the prospects for worthwhile redevelopment, offsetting the costs of decommissioning and ensuring that best use is made of the material, land and human resources associated with each facility. A range of factors to consider has been identified and illustrated using case studies drawn from Member States, and practical guidance has been provided for involved parties to help promote successful and effective redevelopment of decommissioned nuclear installations in the future.
Subject Classification: 0804 - Waste management
STI/DOC/010/445
ISBN: 92-0-111905-4
Publication Date: 16-3-2006
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.
Subject Classification: 0804 - Waste management
STI/DOC/010/446
ISBN: 92-0-112605-0
Publication Date: 20-7-2006
Taking into consideration the work done to date on research reactor decommissioning, it is timely to provide a basis for ongoing and intended activities in this field. An evaluation of the state of the art, trends and current issues is desirable. This report reviews, from a historical perspective, decommissioning projects completed in recent years or under way, and assesses progress as well as open and new issues. It is meant to facilitate timely, safe and efficient completion of decommissioning projects for research reactors by highlighting technologies and planning or management methodologies, and suggesting ways to overcome expected issues. The report includes a CD-ROM providing details of several hundred research reactor decommissioning projects.
Subject Classification: 0604 - Research reactors; 0804 - Waste management
STI/DOC/010/448
ISBN: 92-0-101506-2
Publication Date: 19-2-2007
This report explains the general approach to plant life management (PLiM), shows and defines the relationship between nuclear power plant maintenance and PLiM, assembles a list of good practices and formulates guidelines for ageing management of critical structures, systems and components. Additionally, the issues of PLiM for long term operation are discussed in terms of human, technological, economic and regulatory aspects, as well as the importance of the exchange of information regarding lessons learned. PLiM is not only a technical system but is also an attitude of the owners to retain plants in operation as long as possible from a safety and business point of view. Asset management is thus a significant parameter and driving force for PLiM implementation.
Subject Classification: 0702 - Nuclear power operations
STI/DOC/010/449
ISBN: 92-0-101706-5
Publication Date: 1-3-2007
More competitive energy markets have had significant implications for nuclear power plant (NPP) operations, including among others the need for more efficient use of resources and more effective management of plant activities such as on-line maintenance and outages. Outage management is a key factor for safe, reliable and economic NPP performance. It involves many aspects: plant policy, coordination of available resources, nuclear safety, regulatory and technical requirements, and all activities and work hazards, before and during the outage. The IAEA has produced this report on NPP outage management strategies as both a summary and an update to a series of technical publications related to practices regarding outage management and cost effective maintenance. The aim of this report is to identify good practices in outage management: outage planning and preparation, outage execution and post-outage review. This report aims to communicate these practices in a way that can be used by operating organizations and regulatory bodies in Member States.
Subject Classification: 0702 - Nuclear power operations
STI/DOC/010/450
ISBN: 92-0-101806-1
Publication Date: 5-12-2006
Radioactively contaminated sites often cannot be remediated to residual levels of contamination that are not of concern and released for unrestricted use. Residual contamination, buried wastes and other hazards may remain after cleanup is complete, for several reasons: technical limitations, economic feasibility, worker health and safety issues, or prevention of collateral environmental impacts. An optimization between social and economic cost and level of protection has to be found. Hence, maintenance of institutional control is likely to be required for very long periods of time. The present publication discusses the relevant issues and approaches to tackle the conceptual, managerial and technical problems of maintaining institutional control over possibly hundreds or even thousands of years. These provisions and processes for maintaining institutional control over prolonged periods of time and for managing the radiological liabilities are often referred to as stewardship.
Subject Classification: 0701 - Nuclear power planning and economics; 0800 - Nuclear fuel cycle and waste management
STI/DOC/010/456
ISBN: 92-0-112406-6
Publication Date: 1-3-2007
This report provides information and discussion on planning, methodologies and technologies for retrieval and reconditioning of radioactive wastes recovered from old, inadequate disposal or storage facilities. The objective of such projects is to improve waste safety and security in accordance with modern requirements. Selected international experiences in waste retrieval and recovery projects are included. The report serves as a guide for storage and disposal facility personnel responsible for the organization and implementation of waste retrieval and reconditioning projects to optimize planning, selection and use of available and applicable technologies and resources.
Subject Classification: 0804 - Waste management
STI/PUB/1127
ISBN: 92-0-111102-9
Publication Date: 25-3-2002
This Safety Report compares the requirements of IAEA Safety Series No. 50-C/SG-Q, Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Installations (1996), with the ISO 9001:2000 standard issued by the International Organization for Standardization. It identifies the main differences between the ISO quality standards and the additional requirements and guidance contained within the IAEA standard. It also provides information and guidance that may be considered when ISO 9001:2000 and ISO 9004:2000 are utilized by the nuclear industry. Contents: 1. Introduction; 2. Standards used in the comparison; 3. Application of IAEA 50-C-Q and ISO 9001:2000 standards; 4. Major differences and correlations; 5. Guidance for the use of ISO 9001:2000; Appendix I: Coverage of IAEA Code 50-C-Q basic requirements in IAEA Safety Guides 50-SG-Q1 to Q14; Appendix II. Correlation between the basic requirements of IAEA Code 50-C-Q and the requirements in ISO 9001:2000; Appendix III. Correlation between IAEA Safety Guides 50-SG-Q1 to Q14 and the requirements in ISO 9001:2000.
Subject Classification: 0704 - Quality assurance
STI/PUB/1147
ISBN: 92-0-118502-2
Publication Date: 8-1-2003
This report is the thirty-third in the Agencys series of annual reports on operating experience with nuclear power stations in Member States. It is a direct output from the Agencys Power Reactor Information System (PRIS) and contains data on electricity production, overall plant operating performance and plant outage during 2001 for individual plants. In addition to annual performance data and outage information, the report contains a historical summary of performance and outages during the lifetime of individual plants and figures illustrating worldwide performance and statistical data. The PRIS databank is available free of charge to IAEA Member States through its products PRIS-PC, MicroPRIS and the PRIS page on the Internet (http://www.iaea.or.at/programmes/a2). PRIS-PC allows direct access to the database via the Internet. MicroPRIS contains a subset of the PRIS database. Both products are distributed through the Internet and on CD-ROM to IAEA Member States. Contents: 1. Introduction; 2. Nuclear power station units in Member States; 3. Definitions; 4. Figures; 5. Abbreviations; 6. Data sheets on individual nuclear power station units.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/1155
ISBN: 92-0-105303-7
Publication Date: 11-8-2003
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/1163
ISBN: 92-0-108603-2
Publication Date: 20-10-2003
When facing the decision of closing nuclear power plants (NPPs) before expiration of their operating licences, it is important that the same safety measures are applied to management concerns for strategic planning as are applied to technical reviews. These management and organizational issues are fundamental to any future decommissioning process. Managers at sites that decide to close early may be working to cope with management of change issues arising during the transition from operation to decommissioning as they monitor resource and competence needs, as well as staff morale and technical issues. If these issues are not treated satisfactorily, they can have significant safety consequences. The organization often must address all these challenges with little guidance or experience and with reduced resources. This Safety Report has been developed with the support of experts from regulatory, operating and engineering organizations and is intended for managers dealing with the decision to shut down plants prior to expiration of their licences. It provides guidance for senior managers in the area of strategies, personnel involvement, communications, interface with the regulatory body and experiences that may be used as States face challenges in managing the multiple tasks associated with early closure decisions.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/1174
ISBN: 92-0-111703-5
Publication Date: 20-10-2003
This publication is the thirty-fourth in the IAEAs series of annual reports on operating experience with nuclear power stations in Member States. It is a direct output from the IAEAs Power Reactor Information System (PRIS) and contains data on electricity production, overall plant operating performance and plant outage during 2002 for individual plants. In addition, the report contains a historical summary of performance and outages during the lifetime of individual plants and figures illustrating worldwide performance and statistical data.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/1197
ISBN: 92-0-107404-2
Publication Date: 31-10-2005
Subject Classification: 0301 - Physics; 0700 - Nuclear power
STI/PUB/1212
ISBN: 92-0-113904-7
Publication Date: 13-9-2005
This book contains the proceedings of a conference organized by the IAEA and hosted by the Government of Chile through the Atomic Energy Commission of Chile. The purpose of the conference was to foster the exchange of information on current research reactor concerns related to safety, operation, utilization, fuel management and decommissioning, as well as to provide a forum for reactor operators, designers, managers, users and regulators to share experience, exchange opinions and discuss options and priorities.
Subject Classification: 0604 - Research reactors; 0800 - Nuclear fuel cycle and waste management
STI/PUB/1219
ISBN: 92-0-114304-4
Publication Date: 18-1-2005
This report is the thirty-fifth in the IAEAs series of annual reports on operating experience with nuclear power stations in Member States. It is a direct output from the IAEAs Power Reactor Information System (PRIS) and contains data on electricity production, overall plant operating performance and plant outage during 2003 for individual plants. In addition to annual performance data and outage information, the report contains a historical summary of performance and outages during the lifetime of individual plants and figures illustrating worldwide performance and statistical data.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/1222
ISBN: 92-0-116204-9
Publication Date: 14-4-2005
Subject Classification: 0700 - Nuclear power; 0701 - Nuclear power planning and economics; 1300 - Environment
STI/PUB/1224
ISBN: 92-0-102905-5
Publication Date: 23-9-2005
This publication contains the proceedings of an international symposium on Disposal of Low Activity Radioactive Waste held in Córdoba, Spain, 1317 December 2004. The topical issues addressed by the symposium were: policies and strategies for low activity radioactive waste; very low activity radioactive waste; low activity radioactive waste from decommissioning; long lived low activity radioactive waste and other materials; and unique low activity radioactive waste. These proceedings include the keynote addresses, papers on topical issues, records of panel discussions, Chairs summaries of the five topical sessions, the symposium Chairs general summary and symposium findings. A CD containing the contributed papers and a list of participants of the symposium is included.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/1228
ISBN: 92-0-104305-8
Publication Date: 24-11-2005
The legacies of past uranium mining and milling continue to be of concern and require assessment and remedial action. This problem has been recognized in many parts of the world over the past three decades, but has received increased attention since the end of the Cold War. Considerable effort and resources have been expended in dealing with this legacy. However, it has to be noted that the search for uranium has covered almost all countries on the globe. The result in some countries is a legacy of numerous small scale mines and mills. For economic and other reasons, including less stringent environmental standards and awareness at the time, these operations may not have been properly closed out and made safe. The remediation strategies and techniques developed by major problem holders, such as the USA or Germany, often would be out of scale for the problems in other countries. Therefore an international workshop was organized in Lisbon from 11 to 13 February 2004 as a forum for the exchange of views and experiences of countries with smaller scale uranium mining legacies.
Subject Classification: 0801 - Uranium ore processing; 1300 - Environment
STI/PUB/1235
ISBN: 92-0-110005-1
Publication Date: 17-5-2006
This conference provided a forum for professionals and decision makers in the nuclear sector, comprising industry, governments and academia as well as professionals in the knowledge management and information technology sectors. The goals of the conference were: to exchange information and share experience on nuclear knowledge management, comprising strategies, information management and human resource development, and to identify lessons learned and to embark on the development of new initiatives and concepts for nuclear knowledge management in IAEA Member States. Keynote papers delivered by leading experts in the field, industrial leaders and governmental officials covered important aspects of nuclear knowledge management, and the sessions were devoted to: covering managing and preserving nuclear knowledge; managing nuclear information; human resources for the nuclear sector; and networking education and training.
Subject Classification: 0705 - Qualification and training of personnel
STI/PUB/1236
ISBN: 92-0-110105-8
Publication Date: 29-5-2006
Subject Classification: 0705 - Qualification and training of personnel
STI/PUB/1237
ISBN: 92-0-114305-2
Publication Date: 19-12-2005
This report is the thirty-sixth in the IAEAs series of annual reports on operating experience with nuclear power stations in Member States. It is a direct output from the IAEAs Power Reactor Information System (PRIS) and contains data on electricity production, overall plant operating performance and plant outage during 2004 for individual plants. In addition to annual performance data and outage information, the report contains a historical summary of performance and outages during the lifetime of individual plants, figures illustrating worldwide performance and statistical data.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/1247
ISBN: 92-0-104906-4
Publication Date: 1-9-2006
Subject Classification: 0700 - Nuclear power
STI/PUB/1248
ISBN: 92-0-105406-8
Publication Date: 25-9-2006
Subject Classification: 0705 - Qualification and training of personnel
STI/PUB/1252
ISBN: 92-0-106506-X
Publication Date: 21-8-2006
This publication establishes requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. It details the planned and systematic actions necessary to provide adequate confidence that all these requirements are satisfied. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement.
Subject Classification: 0603 - Nuclear power plants; 0701 - Nuclear power planning and economics
STI/PUB/1253
ISBN: 92-0-106606-6
Publication Date: 31-8-2006
This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. Contents: 1. Introduction; 2. Management systems; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix I: Transition to an integrated management system; Appendix II: Activities in the document control process; Appendix III: Activities in the procurement of documents; Appendix IV: Performance of independent assessments; References; Annex I: Electronic document management system; Annex II: Media for record storage; Annex III: Record retention and storage; Glossary.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/1259
ISBN: 92-0-110106-6
Publication Date: 16-10-2006
The IAEA periodically organizes technical meetings and international symposia on all areas of the uranium production cycle. This publication contains the papers and associated material presented at the 2005 international symposium on Uranium Production and Raw Materials for the Nuclear Fuel Cycle Supply and Demand, Economics, the Environment and Energy Security. The topic areas include uranium supply and demand; uranium geology and deposits; uranium exploration; uranium mining and milling; waste management; and environment and regulation.
STI/PUB/1259
ISBN: 92-0-107206-6
Publication Date: 13-9-2006
The IAEA periodically organizes technical meetings and international symposia on all areas of the uranium production cycle. This publication contains the papers and associated material presented at the 2005 international symposium on Uranium Production and Raw Materials for the Nuclear Fuel Cycle Supply and Demand, Economics, the Environment and Energy Security. The topic areas include uranium supply and demand; uranium geology and deposits; uranium exploration; uranium mining and milling; waste management; and environment and regulation.
Subject Classification: 0801 - Uranium ore processing
STI/PUB/1260
ISBN: 92-0-107306-2
Publication Date: 29-11-2006
This publication is set within the context of current trends whereby nuclear power plants (NPPs) are extending their operation beyond their original licence period. Complexities, including the fact that older NPPs may now be in a better technological condition than when they first went into operation, are considered. This publication addresses material degradation, in particular flow accelerated corrosion, with details of past incidents. The main results and lessons learned from incidents or accidents associated with material degradation are identified wherever weaknesses in the associated management processes of NPP operation have been involved. The aim of this publication is to highlight what operators, owners and regulators should do to prevent or decrease the risk of occurrences and to enhance maintenance and inspection activities in the future.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/1280
ISBN: 92-0-112506-2
Publication Date: 2-2-2007
This edition is the thirty-seventh report in the IAEAs series of annual reports on operating experience with nuclear power stations in Member States. The first publication was issued in 1970. It is a direct output from the IAEAs Power Reactor Information System (PRIS). It contains information on electricity production and overall performance of individual plants during 2005. In addition to annual information, the report contains a historical summary of performance during the lifetime of individual plants and figures illustrating worldwide performance of the nuclear industry. This is the first such report issued in an electronic version on CD-ROM which provides enhanced features for data search and analysis.
Subject Classification: 0702 - Nuclear power operations
STI/PUB/960
ISBN: 92-0-201004-8
Publication Date: 31-3-2004
This Safety Guide, a companion document to Safety Series Nos 35-S1 and 35-S2, is part of a set of publications in the IAEA Safety Series dealing with all the important areas of research reactor safety which includes Safety Standards, Safety Guides and Safety Practices. This guide presents guidelines, approved by international consensus, for the preparation, review and assessment of the safety documentation (Safety Series No. 35-S1) and for the preparation of the Safety Analysis Report (SAR) (Safety Series No. 35-S2). In addition, it is most applicable during the design and construction stages of research reactors, as well as during relicensing or reassessment of already existing reactors. Contents: 1. Introduction; 2. Requirements for safety assessment in the licensing process for a research reactor; 3. Preparation of the safety analysis report; 4. Performance of the review and assessment; Appendix: Contents of a Safety Analysis Report; Annex I: Safety analysis approach and methods; Annex II: Examples of input parameters and initial conditions; Annex III: Examples of items to be considered in the reactor description; Annex IV: Typical sources of radioactive material or radiation fields in a research reactor.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/960
ISBN: 92-0-404503-5
Publication Date: 8-8-2003
This Safety Guide, a companion document to Safety Series Nos 35-S1 and 35-S2, is part of a set of publications in the IAEA Safety Series dealing with all the important areas of research reactor safety which includes Safety Standards, Safety Guides and Safety Practices. This guide presents guidelines, approved by international consensus, for the preparation, review and assessment of the safety documentation (Safety Series No. 35-S1) and for the preparation of the Safety Analysis Report (SAR) (Safety Series No. 35-S2). In addition, it is most applicable during the design and construction stages of research reactors, as well as during relicensing or reassessment of already existing reactors. Contents: 1. Introduction; 2. Requirements for safety assessment in the licensing process for a research reactor; 3. Preparation of the safety analysis report; 4. Performance of the review and assessment; Appendix: Contents of a Safety Analysis Report; Annex I: Safety analysis approach and methods; Annex II: Examples of input parameters and initial conditions; Annex III: Examples of items to be considered in the reactor description; Annex IV: Typical sources of radioactive material or radiation fields in a research reactor.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/961
ISBN: 92-0-203505-9
Publication Date: 25-5-2005
This Safety Guide, part of a set of publications in the IAEA Safety Series dealing with all the important areas of research reactor safety which includes Safety Standards, Safety Guides and Safety Practices, develops the general concepts presented in Safety Series Nos 35-S1 and 35-S2 and should be read in conjunction with them. This Safety Guide presents guidelines for the safe utilization and modification of research reactors to ensure that these projects are implemented without undue risks to personnel, the public, the environment or the reactor. While the Safety Guide is most applicable to existing reactors, it is also recommended for use by organizations planning to put a new reactor into operation. Contents: 1. Introduction; 2. Organization and responsibilities; 3. Safety assessment, categorization and approval routes; 4. General and specific safety requirements for design; 5. Pre-implementation phase of a utilization or modification project; 6. Implementation phase of a utilization or modification project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety requirements for experiments; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor installations; 11. Quality assurance of experiments and modifications; Annex I: Categorization criteria; Annex II: Justification of a project.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors