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Radioactive Waste Management
The Role of Modelling - Workshop Proceedings, La Coruña, Spain 24-26 August 2005
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OECD, Nuclear Energy Agency. Published by : OECD Publishing
, Publication date: 23 Feb 2007
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Pages: 191
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Language: English
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Version: Print (Paperback) + Free PDF
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ISBN: 9789264006645
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OECD Code: 662007021P1
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Price:
€45 | $63 | £40 | ¥5800 | MXN810
, Standard shipping included!
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Availability: Available (Print on Demand)
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Other Versions:
E-book - PDF Format
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In the deep disposal of radioactive waste, the presence of several barriers serving complementary safety functions enhances confidence that the waste will be isolated and contained to protect human health and the environment. The barriers include the natural geological barrier and the engineered barrier system (EBS). The EBS itself may comprise a variety of sub-systems or components, such as the waste form, container, buffer, backfill, seals and plugs. These proceedings include the main findings and presented papers from the third NEA-EC workshop on engineered barrier systems, which focused on the role of EBS modelling in the safety case for deep disposal. The workshop examined the modelling tools currently available and identified complex areas of assessment in which further dialogue is needed.
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Executive Summary
1. Introduction
-The NEA EBS Project
-Background to the Workshop on the Role of Modelling
-Report Structure
2. Workshop Objectives and Structure
3. EBS Modelling in the Context of the Safety Case
-Keynote Papers
-EBS Modelling within National Radioactive Waste Disposal Programmes
-Plenary Discussion
4. Working Group Findings
-Working Group A: Process Models
-Working Group B: Performance Assessment and safety Assessment Models
-Working Group C: Interactions between PA/SA Models and Process Models
-Working Group D: Role of Modelling in EBS Design and Optimisation
5. Workshop Conclusions and Recommendations
-Conclusions
-Recommendations
6. References
Appendix A. Workshop Agenda
Appendix B. Papers Presented at the Workshop
-NF-PRO: An Integrated Project on Key-Processes and their Couplings in the Near-Field of a Reponsitory for the Geological Disposal of Vitrified High-Level Radioactive Waste and Spend Fuel by A. Sneyers and G. Volckaert
-Lessons Learnt from the Development and Application of Reactive Solute Transport and Geochemical Models of Differenct Levels of Complexity for the EBS by J. Samper, L. Montenegro, L. Zheng, C. Yang, and J. Alonso
-SR-CAN: Preliminary Feedback to Canister Fabrication, Repository Design and Future R&D by A. Hedin and P. Sellin
-The Impact of Alternative Spend Fuel Dissolution MOdels on Calculated Releases from the EBS - Some Insights from the Oplay Safety Case by L. H. Johnson and J. W. Schneider
-The Role of Safety Functions, Scoping Calculations, and Process Models in Supporting the Choiceof a Reference Design for Belgian Higher Level Waste and Spent Fuel Disposal by P. De Preter, J. Bel, . Gens, P. Lalieux and S. Wickham
-Treatment of Drift Seal Performance in the Long-Term Safety Assessment for a Repository in a Salt Formation by U. Noseck, D. Becker, A. Rugel, Th. Meyer, R. Mauke and J. Wollrath
-Modelling Sorption on Bentonite - Relation of Mechanistic Understanding to Conventional Kd Approaches for PAs by M. Ochs
-Modelling Decisions for a Cementitious Repository for Long-Lived ILW (TRU) by L.E. F. Bailey, A. J. Hooper, and M. J. Poole
-The Integration and Abstraction of EBS MOdels in Yucca Mountain Performance Assessments by S. D. Sevougian, V. Jain, and A. Van Luik
-EBS Modelling for the Development of Repository Concepts, Tailored to Siting Environments by K. Ishigura, H. Ueda, K. Wakasugi, Y. Sakabe, K. Kitayama, H. Umeki, and H. Takase
Appendix C. Membership of Working Groups
Appendix D. List of Participants
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