- •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
Repository implementation |
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tunnels could represent a preferential pathway for groundwater and, hence, excavation work in a repository is often planned to be carried out using techniques such as full-face drilling or ‘‘soft’’ blasting that do less damage.
The duration of the construction phase can be a few to several years, depending upon the extent of the disposal area to be prepared before waste emplacement begins. A common feature of construction plans is that excavation of additional disposal space continues in parallel with waste emplacement activities since these extend over many years. In this case, excavation and emplacement activities, if running in parallel, should be separated spatially because of the strict radiation protection requirements during operation. Excavation produces rock spoil to be managed on the surface, but the volumes involved are far lower than in conventional mining.
7.3.6. Operation
During the operational phase, radioactive waste is transported to the repository site, encapsulated in a disposal overpack (if the facilities for encapsulation are located at the repository site and not at another location), transferred underground and emplaced in the final disposal configuration. The impacts on the surface environment during this long phase are similar to any other medium-size industrial undertaking. In the repository, two methods of working have been proposed. One implies that the space around emplaced waste packages (whether in tunnels, caverns or deposition holes) is continually packed with backfill material. The advantage of proceeding in this way is that the final physical and chemical environment is regained sooner – and this environment has been chosen to minimise corrosion, etc. to the containers. The disadvantage is that the waste packages can no longer be visually inspected and are less easily retrieved, should one wish to do this. For this reason, some geological disposal projects (e.g., at Yucca Mountain) foresee that the tunnels are kept open for a hundred years or more, with backfilling taking place only at repository closure. Other concepts (e.g., in Sweden, Finland and Switzerland) propose to backfill progressively as the waste is emplaced.
The issue of retrievability of wastes during both the operational phase and after closure has been the subject of intense discussion over the past few years, with international reports being produced and meetings organised on the topic (e.g., IAEA, 2000). The fundamental question – first raised by the KASAM committee in Sweden (KASAM, 1988) – is whether the additional flexibility in keeping options open by storing wastes retrievably outweighs the safety advantages of having the wastes as completely removed from potential interference as is possible. In practice, the choice is simplified by the fact that engineering methods to allow retrievability are available, even though they become more complex and expensive as the stepwise closure of the repository progresses and with increasing time after closure of the repository. This conclusion must, however, be demonstrated to the public on the basis of specific studies on retrieval concepts and techniques.
7.3.7. Monitoring
Again, this is not an activity that is restricted to a single development phase. In fact, monitoring the natural conditions at the undisturbed site should begin before any major
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excavation work. Monitoring will also continue, both in and around the repository, during the operational phase, since this is obligatory for nuclear installations. The monitoring activities that have given rise to most discussions over the past years are those that may be continued or initiated after completing emplacement and also after all backfilling and sealing is in place.
A basic principle of geological disposal is that a passive safety system is implemented in which safety is guaranteed without active measures being taken by future generations (see also Chapter 3). This approach does not, of course, rule out monitoring activities. In fact, it appears that populations around a newly sealed repository would certainly require some form of monitoring activities to be continued. The rationale is that these could detect any malfunction that could result from processes or events not considered by the repository developer.
There is a continuing debate on how a monitoring programme can be designed to provide relevant, reliable data over long times. The probability of any monitoring results directly indicating a malfunction is ranked as very low by the developers, who believe that there will be no releases for very long times into the future. Scientists argue that some parameters may give indirect indications and that it is, in any case, of interest to monitor the evolution of the repository system. The public simply wants an additional mechanism, beyond the technical arguments of the experts, to enhance their confidence in repository safety. Since the implementation of a reasonable monitoring programme is not a costly item, the debate is not particularly productive. All post-closure phases of geological repositories will certainly begin with a monitoring programme in place.
The principle purpose of a well-designed monitoring plan at a repository is, in fact, not to try and detect ‘‘leakage’’ from the repository. Rather, it is to collect information during the construction and operation of the repository that will aid in understanding its post-closure behaviour. As this information is gained, it provides the basis for staying with the original design concept or, alternatively, modifying the design to adapt to new information.
Activities in the closure phase, as indicated above, may be initiated immediately following emplacement of the last waste package. Alternatively, it may be separated from this by a period of monitoring that could last years or decades. The closure activities themselves involve backfilling and sealing all access routes to the repository. A topical issue related to closure is how the repository site should be marked thereafter. In the geological disposal programmes in the USA (WIPP and Yucca Mountain), a complex system of markers and monuments at the site is foreseen. In addition, documentation on the location and the contents of the repository is planned to be deposited at multiple locations around the globe. In other programmes, no firm decisions on physical markers have been taken, but all are in agreement with the need for properly archiving all necessary data on the repository.
The purpose of the markers is to reduce the probability of inadvertent human intrusion at some far future time. It has, however, been argued that markers are more likely to attract intruders than to warn them off, and that the best defence against inadvertent intrusion is to locate the repository in an area with no natural resources that might attract exploration. In fact, many believe that the most likely type of intrusion is deliberate, because the repository is seen as a resource, for energy, weapons materials, metals or other purposes.
The above, more or less sequential, activities during repository development must be accompanied by some parallel actions that extend throughout.