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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 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.
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 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.
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.
The U.S. Department of Energy (DOE) is preparing an environmental impact statement (EIS) for management of aluminum spent fuel from foreign and domestic research reactors, much of which is highly enriched in uranium-235. This EIS will assess the need for additional treatment and storage facilities at the Savannah River Site to accommodate the receipt of this fuel, and it also will assess and select a treatment technology to prepare this fuel for interim storage and eventual shipment to a repository for disposal. This National Research Council book, which was prepared at the request of DOE's Savannah River Office, provides a technical assessment of the technologies, costs, and schedules developed by DOE for eight alternative treatment options and the baseline reprocessing option. It also provides comments on DOE's aluminum spent fuel disposal program, a program that is slated to last for about 40 years and cost in excess of $2 billion.
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
This book contains papers from a NATO-sponsored workshop in Almaty in September 2005, which discussed safety-related issues of storing spent nuclear fuel. Fifteen papers cover aluminum-clad fuel discharged from research reactors worldwide, while five papers examine stainless steel-clad fuel from fast reactors, and two Zircaloy-clad fuel from commercial light-water reactors.
Purpose ofthe Workshop In the spirit of enhancing developments in science and technology by facilitating international scientific cooperation, the Science Committee of NATO is sponsoring AR W's in several selected priority areas. The objective of this workshop was to discuss what microbial mediated problems have been experienced in the area of nuclear waste management and spent fuel storage. Long term storage of high-level wastes in repositories is just starting in some countries. However, low and medium level wastes have been stored for several decades. In the area of spent fuel interim, storage has been extended at many locations far beyond the intended time. It was a priority of the workshop to examine and discuss what deleterious effects have been observed under these storage conditions or under conditions used in simulated trial tests for predicting material performance under the storage conditions. For example, one chronic problem that was discussed was possibility that microbial influenced corrosion (MIC) could be taking place in the wet storage of spent fuel thereby initiating or accelerating the process of corrosion. Another discussion in the area of waste forms, focused on the presence ofbiofilms which may be breaking down the structure of the waste form and thereby jeopardizing its integrity. The meeting focused on discussing the observations and data collected relating to problems encountered in the storage of these types of wastes, and sharing this information with others that have not monitored their facilities for similar problems.
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.