- •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
Waste sources and classification |
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2.4.2. Medicine, industry and research
2.4.2.1. Medicine
Radionuclides used in nuclear medicine can be categorised into two forms:
Open sources which have relatively low activity and consist of radioactively labelled chemical compounds used for imaging of internal organs, studying of bodily functions and localised irradiation of cancer cells.
Sealed sources (Fig. 2.10) that generally have high activity and are used for irradiation of tumours. Sealed sources are used in two applications: the first is ‘‘brachytherapy’’, where the source is placed directly in, or very near, the tumour; the second is ‘‘teletherapy’’, where very highly active sources of Co-60 or Cs-137 are used externally.
The medical use of radioisotopes (open sources) for diagnosis and treatment results in the generation of mainly L/ILW-SL. Typically, this waste consists of paper, rags, tools, clothing and filters which are contaminated with small amounts of mostly short-lived radioactivity. The majority of these wastes undergo decay storage for periods of months to a few years before being disposed of in conventional landfill sites.
When sealed sources have decayed to a point where they are no longer emitting enough penetrating radiation for use in treatment, they are considered as radioactive waste. Sources such as Co-60 (half-life =5.24 a) are treated as L/ILW-SL, whereas sources containing significant amounts of Ra-226 (half-life =1620 a) are treated as L/ILW-LL as they require storage and geological disposal due to the long-lived radioactivity.
2.4.2.2. Industry
Industries use radioactive sources for a wide range of applications (e.g., Fig. 2.11). When these sources no longer emit enough penetrating radiation for them to be of further use, they are treated as radioactive waste. Sources used in industry are generally short-lived and any waste generated can be disposed of in near-surface disposal facilities. However, if a sufficient number of sources are disposed of together, e.g., thousands of smoke detector Am-241 sources compacted into steel tubes, then this may be classified as L/ILW-LL
As mentioned previously, some industrial activities involve the handling of raw materials such as rocks, soils and minerals that contain NORM.
The main industries that generate these types of wastes are:
Fig. 2.10. Typical sealed medical sources – radium needles and radium Crowe probe (image courtesy of ANDRA).
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D.F. McGinnes |
Fig. 2.11. Typical sealed industrial sources and smoke detectors (utilising americium).
Oil and gas exploration and production – minerals including a wide range of radionuclides, but especially Ra-226, are deposited as scale in piping and oil field equipment, or left as residues in evaporation lagoons or dumps below offshore oil rigs. In fact, it is interesting to note that the oil and gas industry is the main source of radioactive releases to the waters of northern Europe.
Coal contains uranium and thorium, as well as other radionuclides. These radionuclides become more concentrated than in the original coal when this is burned to produce fly ash.
The wastes from the processing of rock containing phosphates to produce phosphate fertilizers result in enhanced levels of naturally occurring uranium, thorium and potassium radionuclides.
Water treatment – some waters, especially mineral waters, contain low levels of uranium and thorium. These radionuclides become concentrated as a result of purification processes that are used to treat the water before its consumption, e.g., filter sludges, ion-exchange resins, granulated activated carbon, etc.
Metal smelting slags, especially from tin smelting, may contain enhanced levels of uranium and thorium series radionuclides.
2.4.2.3. Research
Universities and research establishments use both open and closed sources that require appropriate management and disposal. The majority of sources are of low activity and/or short half-life. However, some exceptions include high-level long-lived sources such as radium-226 and americium-241 used in biological and/or agricultural research, as well as large but shorter-lived Co-60 sources used for radiation research.
Research reactors produce similar wastes to a commercial nuclear power plant, although on a smaller scale, i.e., operational, decommissioning and spent fuel (if not reprocessed).
Due to the continuing development of particle accelerators (e.g., Fig. 2.12), the current generation have beam currents that are now high enough to result in the production of a significant amount of neutrons (leakage of the proton beam results not only in a cascade of nuclides from spallation reactions but also produces secondary neutrons), leading to the activation of a large amount of the materials used in their construction. Following a 40-year operating lifetime of one of the new generation of particle accelerators, the volume of decommissioning waste and its activity is expected to be in the same order of magnitude as for a 1 GW(e) nuclear power plant which has operated over 40 years.