The important role and performance of engineered barriers in a UK geological disposal facility for higher activity radioactive waste
Graphical abstract
Introduction
The long-term management of radioactive waste has not been straightforward in the UK. Public concern over the long-term behaviour of radioactive waste and its possible impact on the health of future generations has led to the rigorous evaluation of all disposal options (Committee on Radioactive Waste Management, 2006). International consensus is that the safest, most comprehensive option for the long-term management of higher activity radioactive waste (HAW) is deep geological disposal (Nuclear Energy Agency, 2008). The UK, Welsh and Northern Irish Governments’ initially supported this approach, with the intention to dispose of HAW in a geological disposal facility (GDF), and this has since been written into UK and Welsh policy (Department for Environment, Food & Rural Affairs, 2008). As of April 1, 2019, the UK reported over 100,000 m3 of waste that is classed as HAW (Department for Business Energy & Industrial Strategy, 2019). This contains a small fraction of low-level waste (LLW) unsuitable for near-surface disposal, 102,000 m3 of cementitious intermediate level waste (ILW) and 2150 m3 of vitrified high-level waste (HLW). The latter includes vitrified fission products from the reprocessing of spent nuclear fuel (SNF) and corresponds to approximately 95% (80, 000, 000 TBq) of the total inventory activity; ILW possesses ~5% (4,100,000 TBq) whilst the entire LLW inventory contains only 32 TBq (Department for Business Energy & Industrial Strategy, 2019).
Geological disposal refers to the emplacement of solid radioactive wasteforms in an engineered underground facility, within a stable geological setting, that provides long-term containment and isolation from the biosphere, without impacting on background levels of radioactivity (International Atomic Energy Agency, 2011; Nuclear Energy Agency, 1995). A GDF is an engineered structure, at a depth of between 200 and 1000 m. The minimum depth is required to ensure that the repository will not be affected by forecasted glacial and surface erosion, whilst depths below 1000 m offer little advantage because of increased construction costs and engineering challenge. A GDF is required to isolate HAW from mankind until the radioactivity has decayed to levels where any risk to future generations is acceptably low. It is likely, therefore, that a GDF will need to safely contain radioactive materials for hundreds of thousands of years. This critical isolation function will be provided by combination of geological and engineered barriers. In providing the containment of radionuclides from the biosphere, a multi-layered engineered barrier system shall, as well as facilitating significant radionuclide decay, provide a defence-in-depth that provides the public with confidence in the long-term performance of the GDF. In the UK, three types of geological setting have been identified as suitable generic hosts, comprising: high strength “hard” rock (HSR), lower strength sedimentary rock (LSSR) and evaporites. The interaction between the geology and the engineered barriers is a significant factor in the development of the long-term post closure safety case. Hence a detailed understanding of the interaction between the geology and the engineered barrier materials is essential. This paper explores the role of the engineered barriers and the performance of engineered barrier materials, commenting upon the current level of understanding of the likely lifetime of these barriers under GDF conditions.
Section snippets
Engineered barrier systems
The engineered barrier system (EBS) can be regarded as a collection of individual barriers that provide defence in depth to the migration of radioactive materials from a GDF. The effectiveness of these barriers relies on the performance of the “barrier” materials. The selection of these materials is of paramount importance and will depend upon the type of radioactive waste e.g. cemented ILW, vitrified HLW or SNF and choice of geological setting.
A typical EBS will employ a combination of natural
The role, properties and challenges of engineered barrier materials
As the geological disposal of radioactive waste has not yet been designated under the Nuclear Installations Act (1965) as an activity requiring a nuclear site licence, the UK's regulatory framework for the geological disposal of HAW has yet to be finalised (Nuclear Installations Act, 1965). The precise safety functions to be delivered by the engineered barriers have therefore yet to be determined. In the absence of a GDF safety case, current waste packages, which form part of the EBS, are
Conclusions
This paper reviews the roles and performance of a number of prospective engineered barriers to be utilised in a UK GDF. The engineered barriers perform a number of functions i.e. they provide the necessary defence-in-depth to prevent the radionuclides in the radioactive wastes migrating into the natural barrier (geosphere) surrounding a GDF, whilst also delaying the access of groundwater to the radioactive waste enabling the radioactivity to decay. Some assessments of the long-term risks to
Declaration of competing interest
The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper.
Acknowledgements
This work was supported by the EPSRC (Engineering and Physical Sciences Research Council, UK) and Radioactive Waste Management Ltd through the ICO Centre for Doctoral Training in Nuclear Energy (ICO CDT). [EPSRC NPIF Grant reference number: EP/R512540/1; EPSRC Grant reference number: EP/L015900/1]. The authors would like to thank Dr Andrew Craze and Dr Robert Winsley of Radioactive Waste Management Ltd for their valuable insight.
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2022, Progress in Nuclear EnergyCitation Excerpt :More than 50% of the culturable bacterial isolates were capable of Mn(II) oxidation, and manganese had accumulated within the biofilm (Gopal et al., 2008). The widely accepted plan for high level radioactive wastes (HLW) and intermediate level radioactive wastes (ILW) is a geological disposal facility (GDF) whereby the radioactive waste is emplaced deep (200–1000 m) underground in a multi-barrier system, to prevent the migration of radionuclides to the biospshere and provide protection for over hundreds of thousands of years (Marsh et al., 2021; Morris et al., 2011). The multi-barrier system comprises initially of wastes that are encapsulated e.g. cemented for ILW and vitrification for HLW, with the aim of limiting radionuclide migration via providing a stable, low-solubility matrix.