- •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
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cases were evaluated using a single stylised biosphere situation to convert releases into dose. As in most SAs, it was acknowledged that there will be some modification of the near-surface environment over the very long timescales involved due to a range of factors including climate change and the sensitivity of calculated doses to different stylised climate states was investigated in a number of stand-alone biosphere calculations, each based on the same releases from the geosphere.
6.3.3. Consequence analysis
Having identified the possibilities for system evolution to be considered in the SA, these must be analysed to evaluate their consequences for safety. Although some (usually less likely) possibilities may be discussed partly qualitatively, or by the use of simple approximations, the main effort in consequence analysis is generally on the quantitative modelling of assessment cases.
In most SAs conducted internationally, radionuclide releases from the repository near-field, geosphere transport and biosphere transport, accumulation and dilution are modelled using separate computer codes, coupled together in a ‘‘model chain’’. The near-field code provides a source term for the geosphere code, which in turn provides input (radionuclide release rates as a function of time) for the biosphere code. Figure 6.7 shows the model chain COMP23 ! FARF31 ! BIO42 used in the SR 97 SA (SKB, 1999).
Modelling inevitably involves a certain number of conservative assumptions and simplifications because of the complexity of the systems considered, the impossibility of complete characterisation (particularly in the case of the geosphere), the limited understanding that is available for some processes and the wish to avoid treating some poorly defined uncertainties explicitly. Some processes are well-understood and can be modelled using fairly simple relationships based on fundamental physical and chemical principles, such as Darcy’s Law for groundwater flow, Fick’s Laws for diffusion and the Bateman Equations for radioactive decay and ingrowth. These are incorporated, in some form, into most SA model chains. Other processes are more complex to model and, in some cases, less well-understood, examples being advection in flowing groundwater in highly heterogeneous geological media, the range of radionuclide retardation processes that are grouped together as ‘‘sorption’’ and the transport of radionuclides in association with colloids (Box 6.2). The approach used in many SAs for these processes is to incorporate them in a relatively simple form in the model chain codes and to develop separate, more detailed and realistic models to derive input parameters (e.g., the use of geo/hydro analyses, as illustrated in Fig. 6.7) to provide input parameters, with conservative margins applied to the parameter values to deal with uncertainties.
Some poorly understood processes are less amenable to modelling. There is, for example, considerable uncertainty in the radionuclide transport resistance provided by fractured waste forms (such as blocks of vitrified HLW, which may fracture during cooling after fabrication) and by breached canisters, and the way in which this evolves over time. Most SA models conservatively omit this transport resistance altogether. In many cases, the lack of the necessary model or code to treat a particular phenomenon (like fracturing of the waste form) in detail reflects the fact that uncertainties in the phenomenon are large and are unlikely to be reduced significantly by further R&D
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Fig. 6.7. The model chain COMP23 ! FARF31 ! BIO42 used in the SR 97 SA and supporting models and data that provide input parameters (from Fig. 3–11 of SKB, 1999).
(Chapter 8). Even if more refined models and computer codes were available, a pessimistic case in which, say, the transport resistance was small or negligible might still have to be considered. This reduces the motivation to develop such models or codes in the first place, something which is not easy to explain to the general public (Chapter 9).
Over-simplified models and conservative assumptions have to be used with particular care if an aim of a SA is to support site selection or design optimisation. There may, at a given stage of a programme, be more information (and less uncertainty) about some site or design options compared to others, simply because these have been the focus of more intensive site characterisation and design studies. A conservative approach will tend to be most conservative for the least understood options and there is obviously a danger that this may unduly bias a decision against these options.
Safety assessors are often wary about using the word ‘‘prediction’’ to describe evaluations of the performance and levels of safety provided by a repository. This is because there is a danger that the word may be misinterpreted as meaning precise
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Box 6.2. Transport processes in the geosphere
Advection is the process by which dissolved (or colloidal) species (e.g., radionuclides) are transported by the bulk motion of flowing groundwater. Pressure gradients driving groundwater flow may arise, for example, from variations in the hydraulic head (e.g., in a mountainous site), glacial rebound (e.g., Scandinavian and Canadian Shields) and variations in density associated with salinity and temperature contrasts (e.g., at a coastal or island site). In unsaturated systems, flow occurs under gravity following any period of rainfall. Groundwater flow rates may vary considerably even within a single rock formation due to the heterogeneity in fracture and pore space structures and to friction on flow path walls. The resulting spreading of transported solutes (or colloids) is known as mechanical dispersion.
In contrast, diffusion is the process by which radionuclides will migrate driven by gradients in chemical potential. In advective systems, diffusion causes solute dispersion which, when combined with mechanical dispersion, is called hydrodynamic dispersion. The rate of diffusion is determined by the magnitude of the concentration gradient and the diffusion coefficient of each particular solute. The diffusion coefficient is itself a function of the properties of the rock, such as the tortuosity of pore spaces, the properties of the groundwater and, in particular, its temperature, and the properties of the diffusing species, such as their charge and size.
Figure: The retardation mechanisms that may affect radionuclides in the geosphere (after McKinley and Hadermann, 1984).
(Continued )