- •Preface
- •Acronyms
- •Introduction
- •Background and objectives
- •Content, format and presentation
- •Radioactive waste management in context
- •Waste sources and classification
- •Introduction
- •Radioactive waste
- •Waste classification
- •Origins of radioactive waste
- •Nuclear fuel cycle
- •Mining
- •Fuel production
- •Reactor operation
- •Reprocessing
- •Reactor decommissioning
- •Medicine, industry and research
- •Medicine
- •Industry
- •Research
- •Military wastes
- •Conditioning of radioactive wastes
- •Treatment
- •Compaction
- •Incineration
- •Conditioning
- •Cementation
- •Bituminisation
- •Resin
- •Vitrification
- •Spent fuel
- •Process qualification/product quality
- •Volumes of waste
- •Inventories
- •Inventory types
- •Types of data recorded
- •Radiological data
- •Chemical data
- •Physical data
- •Secondary data
- •Radionuclides occurring in the nuclear fuel cycle
- •Simplifying the number of waste types
- •Radionuclide inventory priorities
- •Material priorities
- •Inventory evolution
- •Assumptions
- •Errors
- •Uncertainties
- •Conclusions
- •Acknowledgements
- •References
- •Development of geological disposal concepts
- •Introduction
- •Historical evolution of geological disposal concepts
- •Geological disposal
- •Definitions and comparison with near-surface disposal
- •Development of geological disposal concepts
- •Roles of the geosphere in disposal options
- •Physical stability
- •Hydrogeology
- •Geochemistry
- •Overview
- •Alternatives to geological disposal
- •Introduction
- •Politically blocked options: sub-seabed and Antarctic icecap disposal
- •Sea dumping and sub-seabed disposal
- •Antarctic icesheet disposal
- •Technically impractical options; partitioning and transmutation, space disposal and icesheet disposal
- •Partitioning and Transmutation
- •Space disposal
- •Icesheets and permafrost
- •Non-options; long-term surface storage
- •Alternatives to conventional repositories
- •Introduction
- •Alternative geological disposal concepts
- •Utilising existing underground facilities
- •Extended storage options (CARE)
- •Injection into deep aquifers and caverns
- •Deep boreholes
- •Rock melting
- •The international option: technical aspects
- •Alternative concepts: fitting the management option to future boundary conditions
- •Conclusions
- •References
- •Site selection and characterisation
- •Introduction
- •Prescriptive/geologically led
- •Sophisticated/advocacy led
- •Pragmatic/technically led
- •Centralised/geologically led
- •Conclusions to be drawn
- •Lessons to be learned (see Table 4.2)
- •Site characterisation
- •Can we define the natural environment sufficiently thoroughly?
- •Sedimentary environments
- •Hydrogeology
- •The regional hydrogeological model
- •More local hydrogeological model(s)
- •Crystalline rock environments
- •Lithology and structure
- •Hydrogeology
- •Hydrogeochemistry
- •Any geological environment
- •References
- •Repository design
- •Introduction: general framework of the design process
- •Identification of design requirements/constraints
- •Concept development
- •Major components of the disposal system and safety functions
- •A structured approach for concept development
- •Detailed design/specifications of subsystems
- •Near-field processes and design issues
- •Design approach and methodologies
- •Design confirmation and demonstration
- •Interaction with PA/SA
- •Demonstration and QA
- •Repository management
- •Future perspectives
- •References
- •Assessment of the safety and performance of a radioactive waste repository
- •Introduction
- •The role of SA and the safety case in decision-making
- •SA tasks
- •System description
- •Identification of scenarios and cases for analysis
- •Consequence analysis
- •Timescales for evaluation
- •Constructing and presenting a safety case
- •References
- •Repository implementation
- •Legal and regulatory framework; organisational structures
- •Waste management strategies
- •The need for a clear policy and strategy
- •Timetables vary widely
- •Activities in development of a geological repository
- •Concept development
- •Siting
- •Repository design
- •Licensing
- •Construction
- •Operation
- •Monitoring
- •Research and development
- •The staging process
- •Attributes of adaptive staging
- •The decision-making process
- •Status of geological disposal programmes
- •Overview
- •Status of geological disposal projects in selected countries
- •International repositories
- •Costs and financing
- •Cost estimates
- •Financing
- •Conclusions
- •Acknowledgements
- •References
- •Research and development infrastructure
- •Introduction: Management of research and development
- •Drivers for research and development
- •Organisation of R&D
- •R&D in specialised (nuclear) facilities
- •Introduction
- •Inventory
- •Release of radionuclides from waste forms
- •Solubility and sorption
- •Waste form dissolution
- •Colloids
- •Organic degradation products
- •Gas generation
- •Conventional R&D
- •Engineered barriers
- •Corrosion
- •Buffer and backfill materials
- •Container fabrication
- •Natural barriers
- •Geochemistry and groundwater flow
- •Gas transport and two-phase flow
- •Biosphere
- •Radionuclide concentration and dispersion in the biosphere
- •Climate change
- •Landscape change
- •Underground rock laboratories
- •URLs in sediments
- •Nature’s laboratories: studies of the natural environment
- •General
- •Corrosion
- •Cement
- •Clay materials
- •Degradation of organic materials
- •Glass corrosion
- •Radionuclide migration
- •Model and database development
- •Conclusions
- •References
- •Building confidence in the safe disposal of radioactive waste
- •Growing nuclear concerns
- •Communication systems in waste management programmes
- •The Swiss programme
- •The Japanese programme
- •Examples of communication styles in other countries
- •Finland
- •Sweden
- •France
- •United Kingdom
- •Comparisons between communication styles in Finland, France, Sweden and the United Kingdom
- •Lessons for the future
- •What is the way forward?
- •Acknowledgements
- •References
- •A look to the future
- •Introduction
- •Current trends in repository programmes
- •Priorities for future efforts
- •Waste characterisation
- •Operational safety
- •Emplacement technologies
- •Knowledge management
- •Alternative designs and optimisation processes
- •Materials technology
- •Novel construction/immobilisation materials: the example of low pH cement
- •Future SA code development
- •Implications for environmental protection: disposal of other wastes
- •Conclusions
- •References
- •Index
218 |
A. Hooper |
It was possible to show, however, that the reactions produced no significant changes in the physical properties of the bentonite. Unfortunately, this study, and most other NA studies like it, are of only limited value as the analogy with a repository is not very close. For example, the temperature in the molten magma is about an order of magnitude greater than that expected in the EBS of a HLW repository and the bentonite mineralogy and physical state, while similar, is not too close to the industrial bentonite used in a repository. This is even more of a problem when recent repository designs which incorporate bentonite-sand mixes, rather than pure bentonite buffers, are considered (see Chapter 5 for details). Clearly then, further R&D work in this area seems appropriate.
8.5.5. Degradation of organic materials
The hyperalkaline chemical and microbial degradation of organic wastes, especially cellulose, produces degradation products that could increase the solubility of actinide elements. For the purposes of repository SAs, it is usually assumed that the end-product of cellulose degradation is iso-saccharinic acid (ISA), which is probably the strongest of several complexants. ISA may be removed from the repository by groundwater flow or it may itself be degraded – ultimately to carbon dioxide and water – by microbial action. In determining the concentration of ISA present, the key parameters are the long-term degradation rate of cellulose and the degradation rate of ISA.
Existing NAs include spills of ‘‘black liquor’’, a waste product of the Kraft paper pulping process. Soil and lake sediments polluted by black liquor have been found to contain several microbial strains capable of metabolising ISA under near-neutral chemical conditions (Bailey, 1986, 1987). Microbes capable of degrading ISA under alkaline conditions have been extracted from alkaline lakes in Africa (Greenfield et al., 1995). However, while these studies indicate that such metabolising bacteria exist, no information is available for repository-relevant hyperalkaline environments. Work has been carried out on microbes at the Maqarin site in Jordan (e.g., West et al., 1995; Pedersen, 2000) and no ISA metabolisers were identified but, as the researchers noted that the methods utilised were not yet optimised for use in hyperalkaline environments, this should not be taken as proof as yet. Additional, focused R&D work on this question at this site would be of use in answering this open question.
8.5.6. Glass corrosion
Borosilicate glass, used to form vitrified HLW, is chosen because of its ability to meet processing requirements for working temperature and viscosity, but also because of its resistance to radiation, its low solubility in water and its ability to take high loadings of fission products.
For any glass, composition is the most important determinant of its durability and, therefore, on the basis of its silica content, which (at around 50 per cent) is broadly similar to that of the borosilicate glasses used for HLW, numerous natural basaltic and archaeological glasses have been studied. The properties of particular interest are its rate of dissolution in groundwater and the nature of the secondary alteration products. Comparisons of the corrosion layers on natural basaltic glass with those found on borosilicate glass that has been reacted with water in the laboratory show them to be
Research and development infrastructure |
219 |
Fig. 8.10. A goblet and decanter made from uranium-rich (up to 5 per cent) glass, potential archaeological analogues of HLW glass (Images courtesy of Ken Tomabechi).
very similar (Lutze, 1988), thus increasing confidence in the laboratory data (although some significant differences in the glass chemistry mean that the analogy should not be pushed too far).
To date, little has been done on trying to assess radionuclide uptake in the secondary clays and, consequently, this mechanism is generally ignored in SA. Further R&D in this area, perhaps along the lines of the work of Crovisier et al. (2003), might be worthwhile, as would be studying glasses which have high radionuclide contents (e.g., Fig. 8.10) and are thus more directly analogous to HLW glasses.
8.5.7. Radionuclide migration
Uranium deposits are an obvious source of long-term information on radionuclide migration. They may be used to examine a wide range of processes invoked in SAs, such as containment by the buffer and the geosphere, redox effects, colloids, microbiology etc. (see, for example, Alexander et al., 2006, for further details). The oldest analogues (described next) offer convincing evidence for the long-term stability of uranium dioxide, an analogue of SF, under repository-relevant conditions.
The Oklo (Gabon) analogue is unique in that it contains natural fission reactors in which nuclear chain reactions took place 2000 million years ago – at that time the fissionable (235U) content of uranium ores was still high enough to induce criticality. The reactors occur in reducing conditions at a sandstone/shale interface; locally they are surrounded by clay that has allowed most of the uranium and some fission products to remain in place over this very long timescale. The Cigar Lake (Canada) analogue is