| Edition |
2nd ed. |
| Description |
1 online resource. |
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text txt rdacontent |
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computer c rdamedia |
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online resource cr rdacarrier |
| Series |
Woodhead Publishing series in energy |
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Woodhead Publishing in energy.
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| Note |
Includes index. |
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Print version record. |
| Summary |
Annotation Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste, Second Edition, critically reviews state-of-the-art technologies and scientific methods relating to the implementation of the most effective approaches to the long-term, safe disposition of nuclear waste, also discussing regulatory developments and social engagement approaches as major themes.Chapters in Part One introduce the topic of geological disposal, providing an overview of near-surface, intermediate depth, and deep borehole disposal, spanning low-, medium- and high-level wastes. Part Two addresses the different types of repository systems - crystalline, clay, and salt, also discussing methods of site surveying and construction. The critical safety issue of engineered barrier systems is the focus of Part Three, with coverage ranging from nuclear waste canisters, to buffer and backfill materials.Lastly, Parts Four and Five focus on safety, security, and acceptability, concentrating on repository performance assessment, then radiation protection, environmental monitoring, and social engagement. Comprehensively revised, updated, and expanded with 25% new material on topics of current importance, this is the standard reference for all nuclear waste management and geological repository professionals and researchers.Contains 25% more material on topics of current importance in this new, comprehensive editionFully updated coverage of both near-surface/intermediate depth, and deep borehole disposal in one convenient volumeGoes beyond the scientific and technical aspects of disposal to include the political, regulatory, and societal issues involved, all from an international perspective. |
| Access |
Legal Deposit; Only available on premises controlled by the deposit library and to one user at any one time; The Legal Deposit Libraries (Non-Print Works) Regulations (UK). WlAbNL |
| Terms Of Use |
Restricted: Printing from this resource is governed by The Legal Deposit Libraries (Non-Print Works) Regulations (UK) and UK copyright law currently in force. WlAbNL |
| Contents |
Front Cover -- Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste -- Related titles -- Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste -- Copyright -- Contents -- List of contributors -- Preface to the second edition -- Preface to the first edition -- 1 -- Introduction to geological disposal of spent nuclear fuels and radioactive waste -- 1 -- Repository 101: multiple-barrier geological repository design and isolation strategies for safe disposal of radioactive ... -- 1.1 Introduction -- 1.2 Multiple-barrier geological repository for radioactive materials -- 1.3 Basic disposal strategies for radioactive materials -- 1.4 Containment of radioactive materials -- 1.4.1 Canister containment -- 1.4.2 Transport time -- 1.4.3 Additional issues -- 1.5 Constraints on concentration of radioactive materials -- 1.5.1 Waste-form dissolution and radioelement solubility -- 1.5.2 Additional waste-form considerations -- 1.5.2.1 Metastability -- 1.5.2.2 Shared solubility for radioelements -- 1.5.2.3 Low-solubility waste form -- 1.5.2.4 Inventory-limited release of radioelements -- 1.5.2.5 High-solubility radioelements -- 1.5.2.6 Trace-element behavior and coprecipitation -- 1.5.3 Temporally distributed containment failure -- 1.5.4 Spatially distributed containment failures -- 1.5.5 Far-field transport -- 1.5.6 Cumulative effect of constraints on concentration -- 1.6 Summary -- References -- 2 -- Effects of very long-term interim storage of spent nuclear fuel and HLW on subsequent geological disposal -- 2.1 Background: commercial spent nuclear fuel storage systems -- 2.2 The need for long-term storage -- 2.3 Regulatory safety requirements -- 2.3.1 General safety functions -- 2.3.2 Aging management approach for licensing. |
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2.4 Potential long-term degradation of dry storage systems-technical issues -- 2.4.1 Data gap analyses -- Approaches to filling the data gaps -- 2.4.2 Systems, structures, and components-specific data gaps for long-term storage-some examples -- 2.4.2.1 Early dry storage field testing -- 2.4.2.2 Potential CSNF cladding embrittlement at higher burnup levels -- 2.4.2.3 Long-term degradation of welded stainless steel canisters -- 2.4.2.4 Addressing bolted lid data gaps -- 2.4.3 Plans to address the data gaps -- 2.4.3.1 Addressing the CISCC data gap for welded SS canister systems -- 2.4.3.2 Addressing the HBU CSNF cladding gap -- 2.4.3.3 Cask or canister replacement -- 2.5 Effects of long-term storage practices on subsequent transportation and disposal -- 2.6 Conclusion -- References -- 3 -- Surface, subsurface, intermediate depth, and borehole disposal -- 3.1 Introduction -- 3.1.1 Historical background to near-surface disposal -- 3.1.2 Current role of near-surface and borehole disposal in the overall context of radioactive waste management -- 3.1.3 Defining the "near-surface": limits to human intrusion -- 3.1.4 Outline of the sections -- 3.2 Safety requirements for near-surface disposal -- 3.2.1 IAEA safety principles and requirements -- 3.2.2 Safety of disposal facilities -- 3.2.2.1 Operational safety -- 3.2.2.2 Postclosure safety -- 3.2.2.3 Safety of mining and milling wastes -- 3.2.3 Significance of the institutional control period -- 3.3 Styles of near-surface disposal -- 3.3.1 General -- 3.3.2 Surface facilities-trenches and engineered vaults -- 3.3.3 Subsurface facilities-silos, caverns, and tunnels -- 3.3.3.1 Intermediate depth disposal -- 3.3.3.2 Deep disposal of LILW -- 3.3.4 Mining and milling wastes -- 3.3.5 Borehole facilities for large and small volume waste packages -- 3.3.6 The IAEA Borehole Disposal Concept for disused sealed sources. |
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3.4 Designing for safety -- 3.4.1 Stakeholder views -- 3.4.2 Waste acceptance criteria -- 3.4.3 Disposal environment -- 3.4.4 Engineered barriers -- 3.4.5 Natural barriers -- 3.4.6 Safety functions -- 3.5 Current issues and future trends -- 3.5.1 Remediation of historical near-surface disposal facilities -- 3.5.2 Intermediate depth disposal -- 3.5.3 Borehole disposal -- 3.6 Sources of further information -- References -- 4 -- Deep borehole disposal of nuclear waste: US perspective -- 4.1 Introduction -- 4.2 Candidate wastes -- 4.3 Siting -- 4.4 Drilling -- 4.5 Emplacement -- 4.6 Seals -- 4.6.1 Bentonite -- 4.6.2 Cement -- 4.6.3 Rock welding -- 4.7 Safety analysis of borehole disposal of spent fuel -- 4.8 Safety analysis of borehole disposal of Cs/Sr -- 4.9 Preclosure safety -- 4.10 Deep borehole field test -- 4.11 Characterization borehole -- 4.12 Conclusions -- Acknowledgments -- References -- 5 -- Relevance of underground rock laboratories for deep geological repository programs -- 5.1 Introduction -- 5.1.1 Definition of URLs and their purposes -- 5.1.2 Chapter outline -- 5.2 Types of URLs and their roles in the staged development of repositories -- 5.2.1 Different types of URLs -- 5.2.2 Past and present URLs in the world -- 5.2.3 Evolution of URL investigation programs over time -- 5.3 Basic considerations when planning and designing a URL -- 5.3.1 General requirements for the implementation of a site-specific URL -- 5.3.2 Timing of URL development and the resources required -- 5.4 URLs in the service of public information and knowledge dissemination -- 5.4.1 Public outreach -- 5.4.2 URLs as training platforms and knowledge -- 5.5 Case studies of URL experiments -- 5.5.1 In situ characterization and testing of near-field and far-field processes -- 5.5.1.1 Colloid formation and migration -- 5.5.1.2 Long-term diffusion. |
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5.5.1.3 Large-scale monitoring -- 5.5.2 Large-scale demonstrations of engineered barrier performance -- 5.5.2.1 Full-scale engineered barrier system experiment -- 5.5.2.2 Full-scale emplacement -- 5.6 Concluding remarks and thoughts for the future -- References -- Further reading -- 2 Geological repository systems: characterization, site surveying and construction -- 6 -- Salt repository systems: design development approach at the example of the Gorleben salt dome -- 6.1 Introduction -- 6.2 A brief history of R& -- D for disposal in salt -- 6.3 Repository system in salt -- 6.3.1 Geology -- 6.3.2 Safety approach -- 6.3.3 Repository design -- 6.4 Repository closure -- 6.5 Retrievability -- 6.6 Conclusion -- References -- 7 -- The Yucca Mountain license application -- 7.1 Introduction -- 7.2 Submittal of the Yucca Mountain license application to the Nuclear Regulatory Commission and docketing for formal review -- 7.3 The content of the license application -- 7.3.1 General Information volume -- 7.3.1.1 General description -- 7.3.1.2 Waste forms to be disposed -- 7.3.1.3 Major surface facilities design features -- Initial handling facility -- Aging facility -- Wet handling facility -- Canister receipt and closure facilities -- 7.3.1.4 Major subsurface design features -- Underground excavations -- Waste packages -- Drip shields -- 7.3.1.5 Proposed schedules for construction, receipt, and emplacement of waste -- 7.3.2 Repository safety before permanent closure -- 7.3.2.1 Surface facility design -- 7.3.2.2 Subsurface facility design -- 7.3.2.3 Preclosure safety analysis -- 7.3.3 Repository safety after permanent closure -- 7.3.3.1 The multiple barrier repository system concept -- 7.3.3.2 Upper natural barrier -- 7.3.3.3 Engineered barrier system -- 7.3.3.4 Lower natural barrier -- 7.4 Research and development program to resolve safety questions. |
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7.5 Performance confirmation program -- 7.6 Management systems -- 7.7 The description of the safety of a repository at Yucca Mountain -- 7.7.1 Safety during the operations period -- 7.7.1.1 Features of surface operations facilities that are important to safe operations -- 7.7.1.2 Preclosure safety analysis methodology -- 7.7.1.3 Assessment of potential worker and public radiation health and safety -- 7.7.2 Safety of the repository after permanent closure -- 7.7.2.1 Features of the repository system considered in assessments of long-term performance -- 7.7.2.2 Results of the postclosure total system performance assessment -- 7.7.2.3 Compliance with the final Environmental Protection Agency standard and the Nuclear Regulatory Commission regulation -- 7.8 Conclusions -- 8 -- Assessing long-term stability of the geological environment -- 8.1 Introduction -- 8.1.1 Recent geophysical and weather-related events and lessons learned for geological storage -- 8.2 Long-term volcano-tectonic stability issues -- 8.3 Geochemical stability issues -- 8.4 Potential climate change issues -- 8.5 Using geological, geophysical, and geochemical techniques for quantifying stability -- 8.5.1 Geological mapping -- 8.5.2 Measuring current crustal deformation using GPS -- 8.5.3 Active fault mapping and paleoseismology -- 8.5.4 Historical seismological record -- 8.5.5 Indicators or tectonic uplift or subsidence -- 8.5.6 Geophysical techniques for detecting crustal structure and volcanic intrusions -- 8.6 Modeling long-term stability -- 8.7 Future trends -- 8.8 Summary -- Sources of further information -- Acknowledgments -- References -- 9 -- Far-field process analysis and radionuclide transport modeling for saturated media -- 9.1 Framework -- 9.1.1 Role of the geosphere in a repository system -- 9.1.2 Rock types considered as potential host formations. |
| Subject |
Radioactive waste disposal in the ground.
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Radioactive waste disposal.
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Déchets radioactifs -- Élimination dans le sol.
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TECHNOLOGY & ENGINEERING -- Mechanical.
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Radioactive waste disposal
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Radioactive waste disposal in the ground
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| Added Author |
Apted, Michael J.
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Ahn, Joonhong.
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| Other Form: |
Print version: 008100642X 9780081006429 (OCoLC)959033241 |
| ISBN |
9780081006528 (electronic bk.) |
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0081006527 (electronic bk.) |
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008100642X |
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9780081006429 |
| Standard No. |
AU@ 000061156818 |
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CHBIS 011069532 |
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CHVBK 499775198 |
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GBVCP 889892482 |
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CHNEW 001014310 |
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AU@ 000066135250 |
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