This report results from a Coordinated Research Project on ""Ageing of Materials in Spent Fuel Storage Facilities"". It includes sections on the status of the understanding of the ageing of selected materials and on management of ageing.
The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field.Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management.With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. - Provides a comprehensive and holistic review of the complete nuclear fuel cycle - Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis - Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication
This publication identifies issues and challenges relevant to the development and implementation of options, policies, strategies and programmes for ensuring safe, secure, and effective storage of spent fuel until transport for reprocessing or disposal. The target audience of this publication includes policy and decision makers who need to be aware of the implicit risks and costs associated with decision timing for determining and implementing an end point for spent fuel management (such as reprocessing or disposal) to ensure the responsible and sustainable use of nuclear energy. The publication will assist those within the nuclear industry in communicating the importance of a clear, credible and sustainable spent fuel management strategy and will encourage decision makers to consider different approaches that may be useful in addressing the uncertainties resulting from an unknown storage duration and an undefined end point for spent fuel management.
The importance of recycling the spent nuclear fuel through partitioning processes has been recognized worldwide for increasing and sustaining nuclear energy.
This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-15 and provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facility and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods beyond the original design lifetime of the storage facility that have become necessary owing to delays in the development of disposal facilities and the reduction in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. Guidance is provided on all stages in the lifetime of a spent fuel storage facility, from planning through siting and design to operation and decommissioning. The revision was undertaken by amending, adding and/or deleting specific paragraphs addressing recommendations and findings from studying the accident at the Fukushima Daiichi nuclear power plant in Japan.
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.