- •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
34 |
D.F. McGinnes |
Decay in radioactivity of high-level waste from reprocessing one tonne of spent PWR fuel
Radioactivity (GBq)
107
total
fission products
actinides
106
105
104
Original Ore
103
102
10 |
102 |
103 |
104 |
105 |
106 |
107 |
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Years after separation |
Gbq = 109 becquerel
The straight line shows the radioactivity of the corresponding amount of uranium ore.
NB both scales are logarithmic.
Source: OECD NEA 1996, Radioactive Waste Management in Perspective.
Fig. 2.18. Radioactive waste in perspective: time taken for reprocessed waste to attain the same activity as the original uranium ore from which the spent fuel was produced.
produced is shown in Fig. 2.18. However, it must be pointed out that the specific activities are still significantly different, i.e., the activity is distributed over different volumes (0.11 m3 of vitrified HLW is approximately equivalent to 700 m3 of original uranium ore).
2.7.5. Simplifying the number of waste types
In any national radioactive waste programme, a bewildering range of waste types can arise, based on the waste immobilisation matrix (e.g., type of cement used) or container type (e.g., steel drum, concrete box). To be in the position to perform an efficient (i.e., cost effective) safety assessment, it is therefore necessary to group wastes and summarise their properties into representative waste types. Generally, this can be viewed as a strict application of common sense, e.g., combining HLW waste types with L/ILWSL waste types will not result in a sensible representative waste type. Further, organiccontaining wastes should not be diluted with inorganic-containing wastes due to the differing behaviour of the organics in a post-closure repository. Nor, for example, is it
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Waste sources and classification |
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Table 2.7 |
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Priority key tablea |
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Inventory (see section 2.7.5.1) |
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a The values inserted into this table are illustrative. The position of priority 1 is clear but 2 or 3 will depend on whether more weight is put on the inventory or the material content. Therefore, the positioning of the priority tends to become more subjective the higher the number. However, using such a priority key table, it is possible to identify whether it is wise to group waste types together (to reduce the number of waste types to be considered) and also to prioritise any work that is required in obtaining additional information, etc.
recommended that -wastes be combined with pure -wastes, even if they contain the same type of materials, as the long-lived -wastes require longer periods of immobilisation in a repository than the -wastes.
Although there are many options available for waste combination, one simple way of assessing what should or should not be combined, and to determine where the maximum amount of effort should be invested, is to use a waste priority key table (Table 2.7) where the following material and inventory priorities may be established.
2.7.5.1. Radionuclide inventory priorities
For a L/ILW-SL repository, definitions normally exist which give either average or maximum total or individual radionuclide activity values. Therefore, for the first round of prioritisation, categories can be defined on this basis. For the next inventory when, e.g., total inventories of individual nuclides have been defined, this process can be repeated to consider these additional criteria.
Category 1: >10% of limit
Category 2: 0.1% < inventory values < 10% of limit
Category 3: <0.1% of limit
For L/ILW-LL and HLW, this system is less applicable as the importance of each waste type must be (as far as activity content is concerned) uniformly high and, correspondingly, the level of knowledge should also be as high as possible.
2.7.5.2. Material priorities
Based on the amount (wt%) of organic material in the waste relative to the cement immobilisation matrix, the following type of table (Table 2.8) can be created (please note, however, that these values are merely indicative of an approach, but are not necessarily applicable to a particular disposal programme where such data need to be produced with the input of safety analysis experts).
The classification applies if any one of the criteria is reached within a specific waste type. Again, as for the radionuclide inventories, this sort of approach is more suitable to L/ILW-SL inventories, but can be used for L/ILW-LL as well, i.e., for wastes of similar activity levels,