- •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
8
Waste sources and classification
D.F. McGinnes
NOK (Northeast Switzerland Power Company), Baden, Switzerland
2.1. Introduction
The objective of this chapter is not only to describe the various sources of radioactive wastes, their classification and how they are conditioned for disposal, but also to examine issues that are of interest in a broader environmental context.
It should be recognised by the fact that the topic ‘‘waste sources and classification’’ is addressed at the beginning of this book that it is one of the key elements in any disposal programme. Without a proper understanding of radioactive wastes, namely their chemical, physical and radiological properties, it is not possible to correctly design a repository, or to assess the safety of any proposed facility for the handling, storage or disposal of these materials. The direct implication of this statement is that, without a reasonable inventory that bounds the waste types that are expected to be disposed of in a planned repository, the situation could arise that some of the waste may not, at the time of disposal, meet the repository acceptance criteria and hence not be placed in a given repository.
To this end, one of the basic requirements for a disposal programme is the creation of an inventory that documents all radioactive wastes that are expected to arise for disposal. The requirements for such an inventory will form a key part of this chapter.
2.2. Radioactive waste
Radioactive waste is defined by the International Atomic Energy Agency (IAEA, 1994) as ‘‘Any material that contains or is contaminated by radionuclides at concentrations or radioactivity levels greater than the exempted quantities established by the competent authorities, and for which no use is foreseen.’’
However, it should be recognised that one person’s waste may be another person’s resource and this holds true, to a certain extent, for radioactive waste, although it is normally national policy that determines this point.
For spent fuel (SF), some countries define this material as a resource for recycling, and not as a waste, with the intention of separating the uranium and plutonium for re-use as
DEEP GEOLOGICAL DISPOSAL OF RADIOACTIVE WASTE |
2007 Elsevier Ltd. |
VOLUME 9 ISSN 1569-4860/DOI 10.1016/S1569-4860(06)09002-4 |
All rights reserved. |
Waste sources and classification |
9 |
fuel in reactors (see section 2.4.1.4). In other countries, the opposite is true and SF is considered as a waste. However, it should be pointed out that this is generally not a simple decision based on economic assessments and left to the owners of the SF (as would be the case in nearly any other business), but is often based on political considerations. For example, the original governmental policy in Germany in the 1970s and 1980s was that SF could only be produced if contracts existed for its reprocessing. Around 15 years later, this was followed by an unsuccessful governmental attempt to force the cancellation of some of these contracts and a complete ban on reprocessing came into force in 2005. However, a more understandable rationale is that based on security of energy supply. This has recently led to the recommendation in Japan for active commissioning of a domestic reprocessing plant. If this had been left to pure economic forces, the decision would probably have been otherwise. Therefore, whether SF is treated as a waste or not is often a matter of national policy.
2.3. Waste classification
Radioactive waste requires appropriate handling and management to ensure the safety of workers, the general public and the surrounding environment due to the radiation emitted. However, not all radioactive waste produced has the same level of potential hazard.
Classification (or grouping) of radioactive wastes makes it easier to determine how to handle the wastes generated and also helps to identify suitable disposal options. Definitions for the classification of waste vary from country to country and, as such, make comparison difficult (see comments in IAEA (1994) and Vankerckhoven and Mitchel (1998)). To circumvent this, the IAEA has recently implemented a waste management database (NEWMDB, see Csullog et al., 2001), which attempts to harmonise waste declarations (Table 2.1).
However, it should be emphasised that these are general criteria and it is recommended that the pertinent national regulations are examined to determine what applies in any particular country For example, in the UK, which has an operating LLW repository (the Drigg site in Cumbria), the following classifications apply (RWMAC, 1997):
Table 2.1
Details of the waste classes defined by the IAEA (from Csullog et al., 2001)
Waste class |
Typical characteristics |
Possible disposal options |
|
|
|
Exempt Waste (EW) |
Activity levels at or below clearance levels |
No radiological restrictions, |
|
|
normal landfill |
Short-lived |
Restricted long-lived radionuclide concentrations, |
Near-surface or geological |
(L/ILW-SL) |
e.g., long-lived -emitters average <400 Bq/g or |
repository |
|
4000 Bq/g maximum per package |
|
Long-lived |
Long-lived radionuclide concentrations |
Geological disposal facility |
(L/ILW-LL) |
exceeding limitations for short-lived wastes |
|
High-level waste |
Thermal power greater than about 2 kW/m3 and |
Geological disposal facility |
(HLW) |
long-lived radionuclide concentrations exceeding |
|
|
limitations for short-lived wastes |
|
|
|
|