- •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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W.R. Alexander et al. |
glass – long-term corrosion/dissolution rates, secondary product identification.
metal – corrosion products during the short-term oxic (operational) phase and longterm anoxic (post-closure) phase, pitting corrosion rates
bentonite – potential alteration in brines and hyperalkaline leachates, high-temperature effects, long-term durability to low-alkali cement leachates
cements and concretes – long-term leaching behaviour, degree of carbonation, degradation, long-term durability novel formulations (including low alkali cements).
As much of the EBS data are fairly generic, such work is an ideal area for international collaboration and could be supported by, e.g., the EU or the IAEA. Ideally, all such tests would be part of an integrated programme which would include the in situ tests, laboratory and modelling work and natural analogue studies, as this would allow identification of the significant mechanisms and processes on all scales (temporally and physically). Additionally, such an approach would lead to a better understanding of the areas of concern by a wider spectrum of shareholders by providing demonstrations of the key processes over the relevant timescales (see also comments in, e.g., Alexander et al., 1998).
10.3.7. Future SA code development
As noted in Chapter 6, performance/safety assessors are often wary about using the word ‘‘prediction’’ to describe evaluations of the performance and levels of safety provided by a repository (see also comments in Savage, 1995). This is because there is a danger that the word may be misinterpreted as meaning precise predictions of, e.g., the actual release of radioactivity from the repository, the actual rate at which radioactivity from the repository enters the biosphere or radiation doses received by human populations living in the future. In fact, doses and risks calculated on the basis of stylised approaches and simplified models should be interpreted as illustrations based on agreed sets of assumptions for particular scenarios and well-defined, but not necessarily realistic, model assumptions, and not as actual measures of future health detriments and risks (ICRP, 2000).
It may be that, if it appears that an analysis will give results near to or exceeding regulatory guidelines, then effort is spent in developing and testing more realistic models and databases that reduce the level of conservatism, thereby reducing the calculated doses or risks to levels that are well below the relevant guidelines. Future SAs may also use Bayesian logic to allow use of prior knowledge to help assess the likely implications of new design or host rock options (see, e.g., Curtis and Wood, 2004).
Finally, development of new SA codes which would provide more ‘‘transparent’’ (to all stakeholders) assessments have been discussed within the radwaste industry for the last decade. To date, little has been achieved but, as more programmes move towards repository implementation, it seems likely that the pressure to make the black magic of repository SA more accessible (and therefore more understandable) to stakeholders will increase. Indeed, there is an argument that such an opening up of SA would help countermand the ‘‘anti-science/relativist’’ approach to dealing with radwaste which Baverstock and Ball (2005) have accused the UK’s CoRWM of utilising in its assessment of the way forward for the UK radwaste industry.
A safety case needs to be presented in a style that is understandable and useful to its intended audience, taking account of their interests, concerns and level of technical