Understanding And Managing Ageing Of Material In Spent Fuel Storage Facilities
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Understanding and Managing Ageing of Material in Spent Fuel Storage Facilities by International Atomic Energy Agency Pdf
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.
Guidebook on Spent Fuel Storage Options and Systems by IAEA Pdf
This publication is a new edition of Technical Reports Series No. 240, Guidebook on Spent Fuel Storage (1991). It aims to provide guidance on spent fuel storage options, describing the history and observed trends of spent fuel storage technologies, gathering operational experiences and lessons learned. The evolving aspects related to higher burnup and mixed oxide (MOX) spent fuel, and the extension of storage timeframes are detailed. It also includes information on the distribution of the current global inventory of spent fuel by storage systems, a description of (and terminology relating to) available spent fuel storage technologies and different storage facility locations.
Safe and Secure Transport and Storage of Radioactive Materials by Ken Sorenson Pdf
Safe and Secure Transport and Storage of Radioactive Materials reviews best practice and emerging techniques in this area. The transport of radioactive materials is an essential operation in the nuclear industry, without which the generation of nuclear power would not be possible. Radioactive materials also often need to be stored pending use, treatment, or disposal. Given the nature of radioactive materials, it is paramount that transport and storage methods are both safe and secure. A vital guide for managers and general managers in the nuclear power and transport industries, this book covers topics including package design, safety, security, mechanical performance, radiation protection and shielding, thermal performance, uranium ore, fresh fuel, uranium hexafluoride, MOX, plutonium, and more. Uniquely comprehensive and systematic coverage of the packaging, transport, and storage of radioactive materials Section devoted to spent nuclear fuels Expert team of authors and editors
Practices for Interim Storage of Research Reactor Spent Nuclear Fuel by IAEA Pdf
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.
Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Ageing Management for Nuclear Fuel Cycle Facilities by IAEA Pdf
The ageing of structures, systems and components is one of the major challenges faced by nuclear fuel cycle facilities worldwide. This publication is intended to provide information on methods, approaches, practices and strategies for ageing management of nuclear fuel cycle facilities. It provides practical information on the establishment of effective ageing management programmes for nuclear fuel cycle facilities in the operational stage and on ageing management considerations in different stages in the lifetime of a nuclear fuel cycle facility. It also addresses the interface of ageing management with other technical areas and programmes, including maintenance, periodic testing and inspection, equipment qualification and configuration management. Best practice examples on how Member States are addressing ageing issues in nuclear fuel cycle facilities are also provided in this publication.
Author : United States. Department of Energy Publisher : Unknown Page : 108 pages File Size : 54,9 Mb Release : 1980 Category : Government publications ISBN : MINN:30000010520363
Basic Of Transport And Storage Of Radioactive Materials by Wille Frank,Volzke Holger,Saegusa Toshiari Pdf
Safe and secure transport and storage of radioactive materials are essential for sustainable nuclear fuel cycle. The basic technologies are matured, but they have been progressively developed to make transport and storage safer and more secure. Safe and secure culture that encourages a questioning and learning attitude and that discourages complacency should be fostered and maintained. This book provides current basis of safe and secure transport and storage so that those technologies can be readily traced, improved, or modified, if necessary, for and by the future generations. This book overviews current available information in the literature. It also covers advanced technology on similar subjects in the literature. On top of that, new and valuable subjects are introduced for readers to grasp the wide spectrum of the safe and secure transport and storage technology. The contents are arranged and divided into three sections, I: Safety of Transport, II: Safety of Storage, III: Security of Transport and Storage. Contents: Introduction (T Saegusa) Transport: Safety of Transport (G Sert and K Sorenson) Performance of UF6 Packages Under Water Immersion (C Itoh and T Saegusa) Performance of UF6 Packages Under Fire Accident Conditions (G Sert, K Shirai and M Wataru) Radiological and Toxic Impacts and Preparedness for Transport Accidents Involving Release of UF6 (G Sert) Performance of Packages with Transport Frame Under Drop Accidents (C Itoh and T Saegusa) Internal Cask Content Collision During Drop Tests (V Ballheimer, T Quercetti and F Wille) Codification of Ductile Cast Iron Cask (T Saegusa and T Arai) SNF and HLW Package Assessment Under Fire Impac (G Sert and B Eckert) Performance of SNF and HLW Packages Under Immersion Accident (C Itoh and T Saegusa) Aging Management for Transport (Post-Storage Transport of Dual Purpose Package for Spent Fuel) (T Saegusa Chapte) Probabilistic Risk Assessment of Transport of Spent Nuclear Fuel (D J Ammerman) Internal Pressure Build-up of Waste Packages with Wet Contents Under Fire Impact (M Nehrig and F Wille) Radiological Impact of Sea Transport Accident (D Tsumune) Design Loads and Allowable Stresses in Package Attachment Points (G Sert and M Moutarde) Experience Feedback for Assessment of Transport Package Design Safety Reports (G Sert and M-T Caillard-Lizot) Security of Transport and Storage: Security of Transport and Storage (M Hirose, O Loiseau and G Sert) Enhancement of Physical Protection Measures Reflecting the Accident of Fukushima Daiichi NPP and INFCIRC/225/Revision 5 (T Iida, K Tanuma, K Ochiai and T Yamaguchi) Safety of Storage: Safety of Storage (T Saegusa) Long-term Metal Seal Performance (H Völzke and D Wolff) Aging Management Program for Spent Fuel Storage (T Saegusa) Chloride Induced Stress Corrosion Cracking (M Wataru, K Shirai, J Tani, M Goto and T Saegusa) Advanced Monitoring of Containment of Canister (H Takeda) Probabilistic Risk Assessment of Spent Nuclear Fuel Storage (G Bjorkman and T Saegusa) Readership: Advanced graduate students and researchers in the field of nuclear engineering and nuclear waste management. Keywords: Transportation;Storage;Security;Radioactive Material;Technical Basis;Package;CaskReview: Key Features: This book was written by international experts to provide most advanced techn
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.
Understanding and Mitigating Ageing in Nuclear Power Plants by Philip G Tipping Pdf
Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC), along with their relevant analysis and mitigation paths, as well as reactor-type specific PLiM practices. Obsolescence and other less obvious ageing-related aspects in nuclear power plant operation are also examined in depth. Part one introduces the reader to the role of nuclear power in the global energy mix, and the importance and relevance of plant life management for the safety regulation and economics of nuclear power plants. Key ageing degradation mechanisms and their effects in nuclear power plant systems, structures and components are reviewed in part two, along with routes taken to characterise and analyse the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modelling techniques applicable to the study of nuclear power plant materials, as well as the application of advanced systems, structures and components in nuclear power plants. Finally, Part IV reviews the particular ageing degradation issues, plant designs, and application of plant life management (PLiM) practices in a range of commercial nuclear reactor types. With its distinguished international team of contributors, Understanding and mitigating ageing in nuclear power plants is a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers. Introduces the reader to the role of nuclear power in the global energy mix Reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC) Examines topics including elimination of ageing effects, plant design, and the application of plant life management (PLiM) practices in a range of commercial nuclear reactor types
The Ageing of Materials and Structures by Klaas van Breugel,Dessi Koleva,Ton van Beek Pdf
This work is an overview of the state of art on Ageing of Materials and structures in the world. Ageing of materials is a natural phenomenon. Each material we use will age. This ageing will influence the performance of the object where the materials is used. Furthermore, the ageing will be affected by the surroundings in which the object is placed. The main focus of the book is on materials used in infrastructure, energy, buildings and industry. The book in effect establishes the definition of ageing and its main research topics that are relevant for society.
Selection of Away-from-reactor Facilities for Spent Fuel Storage by Anonim Pdf
This publication aims to provide information on the approaches and criteria that would have to be considered for the selection of away-from-reactor (AFR) type spent fuel storage facilities, needs for which have been growing in an increasing number of Member States producing nuclear power. The AFR facilities can be defined as a storage system functionally independent of the reactor operation providing the role of storage until a further destination (such as a disposal) becomes available. Initially developed to provide additional storage space for spent fuel, some AFR storage options are now providing additional spaces for extended storage of spent fuel with a prospect for long term storage, which is becoming a progressive reality in an increasing number of Member States due to the continuing debate on issues associated with the endpoints for spent fuel management and consequent delays in the implementation of final steps, such as disposal.--Publisher's description.
