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The high enriched uranium (HEU) take back programmes will soon have achieved their goals. When there are no longer HEU inventories at research reactors and no commerce in HEU for research reactors, the primary driver for the take back programmes will cease. However, research reactors will continue to operate in order to meet their various mission objectives. As a result, inventories of low enriched uranium spent nuclear fuel (LEU SNF) will continue to be created during the research reactors lifetime and, therefore, there is a need to develop national final disposition routes. This publication is designed to address the issues of available reprocessing and recycling services for research reactor spent fuel and discusses the various back end management aspects of the research reactor fuel cycle.
Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.
This publication, resulting from an IAEA coordinated research project (CRP), provides information about available strategies for research reactor spent fuel management, and presents a decision methodology to assist those selecting among several options, to identify the preferred approach for their specific situation. The decision support tools were developed to consider not only the cost of the possible research reactor spent fuel management strategies, but also the non-economic factors that might influence their selection. Examples of the technologies that are currently used by some IAEA Member States are provided. Additionally, this publication provides information about the Excel based decision-support tools developed as part of this CRP, along with case studies and tutorials to assist users.
This publication provides an introduction to the management of research reactor spent nuclear fuel (RRSNF). Five key areas are discussed: types of RRSNF, characterization data, wet storage considerations, dry storage considerations, and lessons learned and current practices. Information on internationally accepted standards as well as information on aspects such as drying treatment and surveillance programmes are presented, as well as suggestions for further optimization of effective and safe storage of RRSNF through the application of new approaches. The intended users of this publication include industry professionals at operating research reactors and at RRSNF storage facilities who need to identify the most suitable approach for interim storage of spent fuel.
Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
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.
Drawing on the authors' extensive experience in the processing and disposal of waste, An Introduction to Nuclear Waste Immobilisation, Second Edition examines the gamut of nuclear waste issues from the natural level of radionuclides in the environment to geological disposal of waste-forms and their long-term behavior. It covers all-important aspects of processing and immobilization, including nuclear decay, regulations, new technologies and methods. Significant focus is given to the analysis of the various matrices used, especially cement and glass, with further discussion of other matrices such as bitumen. The final chapter concentrates on the performance assessment of immobilizing materials and safety of disposal, providing a full range of the resources needed to understand and correctly immobilize nuclear waste.
The assessment approach described in this publication provides a comprehensive means to determine the status of the infrastructure conditions relevant to all issues detailed in IAEA Nuclear Energy Series No. NP-T-5.1, Specific Considerations and Milestones for a Research Reactor Project. This approach can be used by any interested Member State for self-assessment to identify weaknesses and to determine the additional work needed to develop its national nuclear infrastructure for research reactor programme to an appropriate level. Member States planning to embark on both a research reactor programme and a nuclear power programme, may refer to this publication to ensure that the approach and methodology for the implementation of both programmes is harmonized, efficient and effective.
This publication provides a global overview of the status of spent fuel and radioactive waste management programmes, inventories, current practices, technologies and trends. It presents information on national arrangements for the management of spent fuel and radioactive waste, and on current waste and spent fuel inventories and their future estimates. Achievements, challenges and trends in the management of spent fuel and radioactive waste are also addressed. This second edition has been developed with a basis of national profiles submitted by Member States, complemented with openly available Joint Convention National Reports. The data reported are fully dependent on the input from the States and by the assumptions made to transform these data into the waste classes defined in IAEA Safety Standards Series No. GSG-1, Classification of Radioactive Waste.