- •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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An important constraint on the management option chosen is the economics involved – even if this is rarely emphasised. Based on existing technology, this completely excludes some variants – e.g., space disposal or partitioning and transmutation of long-lived radionuclides (even if they are not excluded by other legal or safety issues). For other options, the economic constraints may be very sensitive to boundary conditions. Thus, despite all the caveats with respect to operational safety, a national programme such as Slovenia’s, which shares one NPP with Croatia and has a very small waste inventory, may well conclude that the cost/risk analysis favours a deep borehole disposal concept over a conventional repository, even if a larger programme, with a large number of NPPs such as France, came to exactly the opposite conclusion.
Deep borehole variants are an example of cases where it is difficult to build a robust concept based on existing technology – but it could be argued that the additional requirements for deep characterisation and operational robustness are within the limits of technological development which can be reasonably expected to occur over the next few decades. Such a situation can be contrasted to space disposal or complete transmutation, which do not appear feasible based on reasonably expected developments of any existing technology5.
Overall, however, it must be accepted that technology has developed in unpredictable ways over the half century in which radwaste management has been an issue and major new developments cannot be precluded. To make these ‘‘superscience’’ options practical, however, such progress would effectively have to involve completely new science (anti-gravity, cold fusion, isotope chromatography, teleportation) which may or may not ever develop. At present, even major advances would appear to be capable of dealing only with a small amount of the least technically problematic waste. Nevertheless, the huge value of the nuclear industry could make even very expensive options feasible. It would, however, also have to be considered if, from the viewpoint of the principle of sustainability, such use of valuable resources of materials, energy and manpower were justified, given the number of more pressing problems facing humanity at present.
Finally, socio-political acceptance must be considered. Even if they can be argued to be less favourable from the viewpoints of safety, practicality or cost, concepts which receive popular acceptance may be the only ones which are feasible in a democracy. This may lead to increased consideration of long-term monitoring, reversibility and institutional control. Under such conditions, the challenge will be to develop an acceptable option which combines the robustness of deep geological disposal with meeting the desires and concerns of the key stakeholders (see also comments in Umeki et al., 2004).
10.3.6. Materials technology
As noted above, the radwaste industry is very conservative, preferring to stick with tried and tested designs but, as more repositories come nearer to fruition, pragmatic thinking is leading to interesting new developments in materials planned for use in either construction, waste immobilisation or both. Here, a couple of examples are briefly
5 For example, in the final report of France’s National Scientific Assessment Committee (CNE, 2006), it was noted that P&T operations represent ‘‘. . . a long process that only makes sense if nuclear energy use continues for at least a century.’’ Adding that, in any case, transmutation of some radionuclides (notably 129I) ‘‘. . . appears particularly difficult’’.
A look to the future |
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presented along with recommendations for long-term testing of these (and other) new materials.
10.3.6.1.Novel construction/immobilisation materials: the example of low pH cement
The problems associated with the use of standard OPC cement in repositories have been covered in Chapters 3, 5 and 8. Briefly, the fact that the cement leachate pH (up to 13.3) is so different from the bentonite pH (8–11) and the host rock pH (near-neutral) means that it is clearly out of (chemical) equilibrium with the other repository components. This will induce reactions which are generally assumed to degrade the barrier behaviour of the nearand far-field components. Consequently, alternative materials (and repository designs) have been examined and, currently, one area of focus is on low-pH cement.
Although traditionally called low-pH cements in the literature (see also Chapter 8), these materials should more correctly be known as low-alkali cements (or, due to their leachate pH values of 10.5–11, at the very least lower pH cements). Although much of the cement grout used by the Romans over two millennia ago was effectively low-alkali cement (see, e.g., the discussions in McKinley and Alexander, 1992; Miller et al., 2000), little interest was shown in the development of modern low-alkali cements until about 20 years ago when AECL began further developing existing cements for use as grouts. In fact, the use of low alkali cement grouts was initially contemplated due to better handling and fracture penetration properties (Mukherjee, 1982) and lower heat generation (e.g., Gray and Shenton, 1998) and, while these properties remain of interest, much work is currently focused on the greater chemical compatibility with bentonite (e.g., JAEA, 2007) and the repository host rocks and preliminary results (e.g., Seidler and Faucher, 2004) from the ongoing EU-funded ESDRED (Engineering Studies and Demonstration of Repository Designs) programme are promising (see also www.esdred.info for further details).
However, one area where some doubt remains as to the relevance of low-alkali cement is that of long-term durability (e.g., Philipose et al., 1991) and this is discussed below.
10.3.6.2.Long-term testing of novel (and existing) materials
It is now widely accepted (e.g., Kickmaier et al., 2005) that conventional laboratory test data combined with empirical or mechanistic extrapolative modelling is not enough on its own. A rigorous safety case needs also to include more qualitative, demonstrative arguments to be accepted by all key stakeholders. Of particular importance here are long-term demonstration tests under relevant, in situ conditions. Such experiments need to consider timescales of decades and can include studies of the behaviour of individual materials used in various EBS designs (such as the low-alkali cements noted above) and also materials in relevant combinations. Such a database is particularly appropriate for building safety cases for repository licensing at the construction, operation and closure stages. Inclusion of qualitative, demonstrative arguments can enhance SA models that are, traditionally, based on conventional laboratory test data combined with empirical/ mechanistic extrapolative modelling. This can increase their chances of acceptance by all key stakeholders.
Generally, for most national radwaste programmes, the timescale until first licensing is several decades away, hence initiation of such long-term studies is now rather urgent if a long-term database is desired. Some materials testing areas which could usefully be examined (but note this is not an exhaustive list) include: