- •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
194
Research and development infrastructure
Alan Hooper
Nirex, Harwell, UK
8.1. Introduction: Management of research and development
8.1.1. Drivers for research and development
Even within the restricted field of radioactive waste management, the range and depth of science that could be investigated is almost unlimited (cf. Sumerling, 2006). If best use is to be made of the available resources, some method is needed to prioritise and target the R&D and, in particular, to decide when to stop work on a specific topic. To explain how this is done, the prime aims of Research and development (R&D) R&D for radioactive waste disposal need to be considered, including:
to provide understanding, data and models for use in various types of assessment: post-closure safety, environmental impact, operational safety, etc;
to support the development and optimisation of repository design, including the selection and specification of the engineered barrier system;
to provide the necessary level of confidence in the safety assessment (noting that this implies a value judgement that will change with societal context).
These aims create a feedback system that can be used to modify the disposal concept and to set the future direction of R&D. This leads to an R&D management system in which (a) R&D provides the data and models for safety assessments, (b) safety assessment outputs are compared with regulatory targets and with stakeholder expectations, and (c) these comparisons generate a need for changes to the disposal concept (cf. Chapter 5) and/or improved understanding, data and models and, hence, new R&D, as illustrated in Fig. 8.1. This type of methodology has the advantage that it can be easily integrated with the stepwise approach to radioactive waste disposal (see also Chapter 7). To illustrate the role of most national R&D work in the overall repository programme, some of the main areas of importance to repository performance will be briefly introduced here and then the role of R&D examined. Where appropriate, comments will also be made on the areas requiring further R&D in the future, but it is not intended to produce an exhaustive list covering all possible areas of R&D as many are very specific to host rock, waste type and EBS design.
DEEP GEOLOGICAL DISPOSAL OF RADIOACTIVE WASTE |
2007 Elsevier Ltd. |
VOLUME 9 ISSN 1569-4860/DOI 10.1016/S1569-4860(06)09008-5 |
All rights reserved. |
Research and development infrastructure |
195 |
Disposal Concept
Gather
R&D understanding, data & models
Safety Assessment – apply the models
Compare outcome with regulatory requirements/ stakeholder expectations for the specified step
Proceed to next step
Fig. 8.1. Relationship between R&D and safety assessment (SA).
8.1.2. Organisation of R&D
There are many kinds of organisations involved in R&D for radioactive waste disposal. The roles of these bodies, and the relationships between them, are diverse and complex, but they are perhaps best described in terms of ‘‘fund providers’’, ‘‘fund disbursers’’ and ‘‘researchers’’ (notwithstanding that some organisations may qualify for all these labels). Figure 8.2 provides a simplified representation of these relationships and helps to describe where the main responsibilities for R&D lie.
At the top of the diagram are the fund providers. These are principally waste producers and the government (including inter-governmental organisations, e.g., the European Commission (EC) through its Research Framework Programmes). Waste producers (e.g., the utilities, central government) typically transfer the funds to an independent fund-holding body. How the funds are raised is often decided by statute; most commonly, it is done through a surcharge on the price of nuclear-produced electricity.
Funds from the waste producers pass to the next level, the radioactive waste implementers and nuclear regulators; this latter category could include both federal and local government. As the prime means of maintaining the regulatory infrastructure, funds also pass to the nuclear regulator from the government. Under some circumstances (e.g., when a licence application is submitted), the implementing body may be required to fund any independent R&D that the regulator may wish to perform. The label ‘‘fund disbursers/researchers’’ indicates that, while these organisations are the main purchasers of R&D, they are also likely to carry out some R&D in-house.
At the foot of Fig. 8.2 are the main research organisations. These consist of commercial organisations, national research institutes and universities. The ‘‘commercial companies’’