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Journal articles on the topic 'Nuclear Decommissioning Authority'
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1
Thomas, Steve. "The UK Nuclear Decommissioning Authority." Energy & Environment 16, no. 6 (November 2005): 923–35. http://dx.doi.org/10.1260/095830505775221597.
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Thomas, Steve. "The organisation & the costs of the decommissioning nuclear plants in the UK." ECONOMICS AND POLICY OF ENERGY AND THE ENVIRONMENT, no. 2 (May 2009): 63–82. http://dx.doi.org/10.3280/efe2008-002005.
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- UK electricity consumers have paid provisions for decommissioning since before 1980 but by 2002, there were still negligible funds available to pay for decommissioning civil nuclear facilities. By then, the two major UK nuclear companies, British Energy and British Nuclear Fuels Limited (BNFL), were both effectively bankrupt. This paper examines: the pre-2002 provisions for decommissioning and how they were lost; the Nuclear Decommissioning Authority, a new public body which took over ownership of BNFL's facilities including the duty to manage their decommissioning and how it expects to carry out and fund decommissioning of its sites; how the re-launched British Energy will contribute to decommissioning its eight plants; and government plans for collecting decommissioning provisions for any new plants.JEL classifications: L50, L38, H23, H44, L71Key words: Nuclear power, decommissioning cost, funding and polluter pays.
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Wareing, Mark. "Demonstrating and Communicating the Value of Nuclear Decommissioning to Society." International Journal of Strategic Decision Sciences 1, no. 3 (July 2010): 1–13. http://dx.doi.org/10.4018/jsds.2010070101.
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The UK Nuclear Decommissioning Authority (NDA) is a Non Departmental Public Body (NDPB) responsible for the remediation of the UK’s civil nuclear liabilities. To secure government funding and demonstrate that the NDA is delivering its mission, it must be able to show that it provides value for money across its estate. Value comes in many forms, such as an improved environment, hazard reduction, changes in sky line, social amenities, money, employment, and so forth. Depending on the perspective of the receiver, and their closeness to the affected area, the weighting placed on the different aspects of value will vary. Therefore, the challenge has been to get a consistent approach that measures value and is broadly acceptable to stakeholders in which different aspects are compared and decisions are made on a national basis.
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M. Sellers, Robin. "Managing the Nuclear Legacy in the UK : Progress towards the Establishment of the Nuclear Decommissioning Authority." Revue Générale Nucléaire, no. 6 (December 2003): 28–33. http://dx.doi.org/10.1051/rgn/20036028.
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Tweed, C. J. "Sound science in geological disposal in the United Kingdom." Mineralogical Magazine 76, no. 8 (December 2012): 2873–79. http://dx.doi.org/10.1180/minmag.2012.076.8.02.
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AbstractThe safe implementation of geological disposal must be underpinned by sound science. This paper describes the approaches taken by the Nuclear Decommissioning Authority Radioactive Waste Management Directorate, the implementing body for geological disposal in the UK, to build an evidence base of scientific data and understanding which is robust to scrutiny and so provides confidence in the safety of geological disposal.
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Wilkinson, P., and F. Barker. "The views and opinions of green stakeholders in respect of the Nuclear Decommissioning Authority." Nuclear Energy 43, no. 6 (December 2004): 311–14. http://dx.doi.org/10.1680/nuen.43.6.311.55680.
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Sanchez-Graells, Albert. "You Can’t be Serious." Nordic Journal of European Law 1, no. 1 (December 6, 2018): 1–23. http://dx.doi.org/10.36969/njel.v1i1.18670.
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This paper offers some reflections on the position advanced by the EFTA Court that a simple breach of EU public procurement law is in itself sufficient to trigger the contracting authority’s liability in damages (Fosen-Linjen). I argue that this position is flawed because it deviates from previous case law of the Court of Justice of the European Union (Spijker), and because it is based on interpretive errors and internal contradictions in the EFTA Court’s reasoning. In criticising the EFTA Court’s Judgment from the perspective of the harmonisation of EU law, I rely on the better view of the UK Supreme Court. The latter held that the liability of a contracting authority for the breach of EU public procurement rules under the remedies directive is assimilated to that of the State under the general EU law doctrine of State liability and thus requires a sufficiently serious breach (Nuclear Decommissioning Authority). My reflections are based on the need to keep procurement damages litigation constrained to its main function and limited to justified cases. I use this normative position to argue against the expansion of private enforcement of EU public procurement law as a correction of the shortcomings in its public enforcement.
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Vines, S., and R. Beard. "An overview of radionuclide behaviour research for the UK geological disposal programme." Mineralogical Magazine 76, no. 8 (December 2012): 3373–80. http://dx.doi.org/10.1180/minmag.2012.076.8.50.
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AbstractIn the UK, radioactive wastes currently planned for disposal in a geological disposal facility (GDF) are intermediate-level waste, some low-level waste and high-level waste. Disposal of other materials, including spent fuel, separated uranium and separated plutonium are also included in the planning of a GDF, if such materials are classified as wastes in the future. This paper gives an overview of the radionuclide behaviour research studies of the Nuclear Decommissioning Authority Radioactive Waste Management Directorate (NDA RWMD). The NDA RWMD's current understanding of the processes that control radionuclide behaviour in groundwater and how the engineered and natural barriers in a GDF would contain radionuclides is presented. Areas requiring further work are also identified.
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Mahon, David, Anthony Clarkson, Simon Gardner, David Ireland, Ramsey Jebali, Ralf Kaiser, Matthew Ryan, Craig Shearer, and Guangliang Yang. "First-of-a-kind muography for nuclear waste characterization." Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 377, no. 2137 (December 10, 2018): 20180048. http://dx.doi.org/10.1098/rsta.2018.0048.
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In the last decade, there has been a surge in the number of academic research groups and commercial companies exploiting naturally occurring cosmic-ray muons for imaging purposes in a range of industrial and geological applications. Since 2009, researchers at the University of Glasgow and the UK National Nuclear Laboratory (NNL) have pioneered this technique for the characterization of shielded nuclear waste containers with significant investment from the UK Nuclear Decommissioning Authority and Sellafield Ltd. Lynkeos Technology Ltd. was formed in 2016 to commercialize the Muon Imaging System (MIS) technology that resulted from this industry-funded academic research. The design, construction and performance of the Lynkeos MIS is presented along with first experimental and commercial results. The high-resolution images include the identification of small fragments of uranium within a surrogate 500-litre intermediate level waste container and metal inclusions within thermally treated GeoMelt® R&D Product Samples. The latter of these are from Lynkeos' first commercial contract with the UK National Nuclear Laboratory. The Lynkeos MIS will be deployed at the NNL Central Laboratory facility on the Sellafield site in Summer 2018 where it will embark upon a series of industry trials. This article is part of the Theo Murphy meeting issue ‘Cosmic-ray muography’.
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Metcalfe, M. P., W. Koch, and G. Turner. "Break-up testing of waste-form materials." Mineralogical Magazine 76, no. 8 (December 2012): 2975–83. http://dx.doi.org/10.1180/minmag.2012.076.8.13.
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AbstractThe Nuclear Decommissioning Authority (NDA) is developing a safety case for the long-term management of higher activity wastes. This includes safety assessments of transport to and operations at the repository. One of the main faults and hazards to be considered is waste package response to impact accidents.The criteria of impact performance for waste packages are based upon activity release of particulates generated from the break up of the waste form during impact. The NDA approach to impact performance is based upon waste package response from finite element modelling in combination with break-up tests.Previous break up research commissioned by the NDA has concentrated on commercial graphite and glass samples. These extended studies, undertaken by the National Nuclear Laboratory in collaboration with the Department of Aerosol Technology of the Fraunhofer Institute of Toxicology and Experimental Medicine, provide break-up data specific to nuclear facilities and waste materials. These include archived unirrradiated graphite used to construct Magnox reactor cores and reflectors, simulant high level waste glass, selected grout formulations and selected metal-in-grout formulations.
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Thornber, Stephanie, Paul Heath, Ewan Maddrell, Martin C. Stennett, and Neil C. Hyatt. "Investigation of Processing Parameters for the Consolidation of Actinide Glass-Ceramic Wasteforms by Hot Isostatic Pressing." MRS Advances 1, no. 63-64 (2016): 4269–74. http://dx.doi.org/10.1557/adv.2017.219.
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ABSTRACTGlass-ceramics were developed initially for the immobilization of miscellaneous Pu-residues at the UK’s Sellafield site from which it was uneconomic to recover Pu for reuse. Renewed interest in the immobilization of a portion of the UK PuO2 stockpile has led to glass-ceramics being evaluated for bulk Pu immobilization. The Nuclear Decommissioning Authority (NDA) in the UK have proposed hot isostatic pressing (HIP) as a potential consolidation technique for the processing of these wasteforms. In this study, zirconolite based glass-ceramics were investigated to determine an optimum formulation. The yield of zirconolite is shown to vary with glass composition and glass fraction, such that a higher Al content favours zirconolite formation. The sample preparation process is discussed to highlight the importance of a high temperature heat-treatment during sample preparation to achieve high quality HIPed wasteforms.
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Vahlund, Fredrik. "Long-term safety of the extended SFR - Methodology and conclusions from the SR-PSU project." MRS Advances 1, no. 61 (2016): 4075–80. http://dx.doi.org/10.1557/adv.2017.192.
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ABSTRACTSince 1988 the Swedish Nuclear Fuel and Waste Management Co. operates a repository for low- and intermediate-level short-lived radioactive waste, SFR, in Forsmark, Sweden. Due to decommissioning of the nuclear power plants additional storage capacity is needed. In December 2014, an application to extend the repository was therefore submitted. One key component of this application was an assessment of post-closure safety of the extended SFR. For this safety assessment, a methodology based on that developed by SKB for the spent nuclear fuel repository was used and the impact of the degradation of repository components, the evolution of the surface system and changes of future climate on the radiological safety of the repository was assessed over a period of 100,000 years. The central conclusion of the SR-PSU safety assessment is that the extended SFR repository meets requirements on protection of human health and of the environment that have been established by the Swedish radiation safety authority for the final disposal of radioactive waste. Furthermore, the design of the repository was shown suitable for the waste selected and the applied methodology suitable for the safety assessment.
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Kowe, R., and S. Norris. "Representation of the biosphere in post-closure assessments for the UK geological disposal programme." Mineralogical Magazine 76, no. 8 (December 2012): 3217–23. http://dx.doi.org/10.1180/minmag.2012.076.8.34.
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AbstractThis paper gives an overview of the Nuclear Decommissioning Authority, Radioactive Waste Management Directorate approach to representing the biosphere in post-closure safety assessment studies. The assessments consider potential releases of radionuclides and chemically toxic substances from a geological disposal facility that may reach the biosphere by transport in groundwater and gas. It gives an outline of the key processes and understanding underpinning the representation of the biosphere and how the biosphere may evolve over the long timescales of relevance to post-closure safety. The current biosphere assessment approach and associated models are supported by research studies and collaboration that ensure they are consistent with international recommendations. Research studies are also commissioned to reduce uncertainty surrounding key contaminants and potential exposure pathways and to help ensure that the approach and models are adaptable and flexible enough to incorporate future developments, as the geological disposal programme moves towards site selection.
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Williams, S. J. "An overview of gas research in support of the UK geological disposal programme." Mineralogical Magazine 76, no. 8 (December 2012): 3271–78. http://dx.doi.org/10.1180/minmag.2012.076.8.40.
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AbstractGases will be generated in waste packages during their transport to a geological disposal facility (GDF), this generation will continue during GDF operations and after GDF closure. The range of gases produced will include flammable, radioactive and chemotoxic species. These must be managed to ensure safety during transport and operations, and the post-closure consequences need to be understood. The two primary post-closure gas issues for a GDF are the need for the system pressure to remain below a value at which irreversible damage to the engineered barrier system and host geology could occur, and the need to ensure that any flux of gas (in particular gaseous radionuclides) to the biosphere does not result in unacceptable risk. This paper provides an overview of the research of the Nuclear Decommissioning Authority, Radioactive Waste Management Directorate into gas generation and its migration from a GDF.
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Norris, S. "An introduction to geosphere research studies for the UK geological disposal programme." Mineralogical Magazine 76, no. 8 (December 2012): 3105–14. http://dx.doi.org/10.1180/minmag.2012.076.8.25.
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AbstractThis paper gives an overview of the geosphere research studies being undertaken by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority. The approach of the RWMD in the current generic phase of the UK managing radioactive waste safely (MRWS) programme is to maintain an understanding of key processes and to carry out research and development into techniques so capability can be built. Although RWMD can demonstrate a general understanding of geosphere processes at this stage in the UK project, it is recognized that this will need to be made site-specific as the MRWS programme progresses. An understanding of the geosphere at the selected site(s) will be an important part of the future programme. Where possible, the RWMD will participate in international studies so that relevant site-based information can be accessed. In this way, the RWMD will be prepared for site-specific work in stage 5 of the MRWS process.
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Beattie, T. M., and S. J. Williams. "An overview of near-field evolution research in support of the UK geological disposal programme." Mineralogical Magazine 76, no. 8 (December 2012): 2995–3001. http://dx.doi.org/10.1180/minmag.2012.076.8.15.
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AbstractThe near field, together with the containment and isolation provided by the geosphere, contributes to the long-term safety provided by a geological disposal facility (GDF) after closure. The different engineered barriers can prevent or limit the release of radionuclides and their migration to the undisturbed host rock or geosphere and are expected to fulfil their post-closure safety functions for many thousands to hundreds of thousands of years. They will continue to contribute to containment after their eventual degradation when there would no longer be confidence that they would continue to fulfil all of their safety functions in their totality. By that time, significant radioactive decay will have occurred, substantially reducing the hazard associated with the wastes. Therefore, demonstration of long-term safety requires an understanding of the evolution of the engineered barriers and the consequences for the generic safety functions that the different barriers provide. This paper provides an overview of the research of the Nuclear Decommissioning Authority Radioactive Waste Management Directorate into the evolution of the near field of a GDF.
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Towler, G., A. E. Bond, S. Watson, S. Norris, P. Suckling, and S. Benbow. "Understanding the behaviour of gas in a geological disposal facility: modelling coupled processes and key features at different scales." Mineralogical Magazine 76, no. 8 (December 2012): 3365–71. http://dx.doi.org/10.1180/minmag.2012.076.8.49.
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AbstractUnderstanding the behaviour of gas in a geological disposal facility (GDF) is an essential component of analysing the facility evolution and long-term (post-closure) safety performance. This includes the impacts of gas on the physico-chemical evolution of the GDF, and the release and migration of radionuclides in water and gas.The Nuclear Decommissioning Authority Radioactive Waste Management Directorate is participating in the EC FORGE (fate of repository gases) project (www.forgeproject.org) and conducting independent research. Key research themes are modelling the impacts of different host rocks on facility evolution including coupled processes, and upscaling the effects of small scale features that can significantly influence the evolution of the whole facility.Recent code developments have enabled coupled processes to be represented more realistically in models. This has significantly advanced understanding of facility evolution, as discussed in this paper, and will improve future assessment models. There is potential to further improve approaches to upscaling the effects of small scale features on strongly coupled processes, within the context of the EC FORGE project.
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Sanchez-Graells, Albert. "Liability threshold for damages in public procurement: the EFTA Court’s Fosen-Linjen saga." Northern Ireland Legal Quarterly 70, no. 4 (January 13, 2020): 511–21. http://dx.doi.org/10.53386/nilq.v70i4.310.
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In this case comment, I explore the two EFTA Court Judgments in the Fosen-Linjen saga and their opposing views on the interaction between EU/EEA rules on procurement remedies and the more general principle of state liability for breaches of EU/EEA law. I review the case law of the Court of Justice of the European Union and, in particular, the perceived inconsistencies between the two 2010 judgments in Strabag and Spijker, which featured very prominently in the legal arguments submitted to the EFTA Court in both Fosen-Linjen cases. I also use the benchmark of the UK Supreme Court’s Nuclear Decommissioning Authority judgment to support the view that Spijker reflects the correct understanding of EU/EEA law and that there should be no further debate about it. I submit that the Court of Justice of the European Union would be well-advised to (re)confirm the position enshrined in Spijker at the earliest opportunity, to avoid any perpetuation of this debate in the context of EU/EEA public procurement law.
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Sanchez-Graells, Albert. "Liability threshold for damages in public procurement: the EFTA Court’s Fosen-Linjen saga." Northern Ireland Legal Quarterly 70, no. 4 (December 12, 2019): OA25—OA35. http://dx.doi.org/10.53386/nilq.v70i4.279.
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In this case comment, I explore the two EFTA Court Judgments in the Fosen-Linjen saga and their opposing views on the interaction between EU/EEA rules on procurement remedies and the more general principle of state liability for breaches of EU/EEA law. I review the case law of the Court of Justice of the European Union and, in particular, the perceived inconsistencies between the two 2010 judgments in Strabag and Spijker, which featured very prominently in the legal arguments submitted to the EFTA Court in both Fosen-Linjen cases. I also use the benchmark of the UK Supreme Court's Nuclear Decommissioning Authority judgment to support the view that Spijker reflects the correct understanding of EU/EEA law and that there should be no further debate about it. I submit that the Court of Justice of the European Union would be well-advised to (re)confirm the position enshrined in Spijker at the earliest opportunity, to avoid any perpetuation of this debate in the context of EU/EEA public procurement law.
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Bond, A. E., S. Benbow, J. Wilson, C. McDermott, and M. English. "Coupled hydro-mechanical–chemical process modelling in argillaceous formations for DECOVALEX-2011." Mineralogical Magazine 76, no. 8 (December 2012): 3131–43. http://dx.doi.org/10.1180/minmag.2012.076.8.27.
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AbstractThe Nuclear Decommissioning Authority Radioactive Waste Management Directorate have been participating in the current DECOVALEX-2011 project (development of coupled models and their validation against experiments) one task of which has been examining the Mont Terri Ventilation Experiment (VE). This long-term (>9 years), field-scale experiment in the Opalinus Clay near the Swiss–French border, was designed to examine the coupled hydraulic–mechanical–chemical changes caused in the tunnel and in the surrounding geology, by the controlled ventilation of a 1.65 m diameter micro-tunnel.In contrast to many conventional benchmarking and validation exercises, a key aspect of the VE as examined in DECOVALEX was that some data were held back and participants were required to make predictions of key metrics for the future evolution of the system. This paper presents an overview of the work conducted by the Quintessa and University of Edinburgh team including selected results. The coupled models developed include multiphase flow, elastic deformation and chemical processes in both detailed and upscaled geometries.The models have been able to replicate the observed desaturation around the tunnel, tunnel deformation and localized failure, vapour migration in the tunnel, and the transition in redox conditions into the host rock.
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Padovani, C., S. J. Williams, and P. Wood. "An introduction to package evolution and criticality research studies relevant to the UK disposal programme." Mineralogical Magazine 76, no. 8 (December 2012): 2881–90. http://dx.doi.org/10.1180/minmag.2012.076.8.03.
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AbstractIn the UK, radioactive wastes currently planned for disposal in a geological disposal facility (GDF) include intermediate level waste, some low level waste and high level waste. Disposal of other materials, including spent fuel, uranium and plutonium is also being evaluated to inform the safety case for a GDF, if such materials were to be classified as wastes in the future. This paper describes the generic safety functions through which waste packages can contribute to the safety case of a GDF in the UK. It describes the engineering approach used or envisaged, in the UK and internationally, to ensure that waste packages retain their safety functions for the required periods of time and summarizes the scientific basis underpinning the current understanding of relevant evolution processes. Where gaps in the knowledge exist, the Nuclear Decommissioning Authority Radioactive Waste Management Directorate has identified specific research activities needed to close out such gaps to a level of maturity sufficient for this stage of the disposal programme (generic). This paper describes the latest results from their R&D programme and presents a summary of the research activities planned to meet the current needs of the disposal programme with specific reference to the topics of package evolution and criticality safety.
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Hoch, A. R., and M. James. "Comparison of alternative approaches to modelling gas migration through a higher strength rock." Mineralogical Magazine 76, no. 8 (December 2012): 3319–26. http://dx.doi.org/10.1180/minmag.2012.076.8.44.
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AbstractThe Radioactive Waste Management Directorate of the UK Nuclear Decommissioning Authority has prepared a generic disposal system safety case (DSSC) that covers a range of possible host rock environments. In many of the waste packages considered in the DSSC, the formation of gases by chemical and microbial processes is likely to occur. In order to demonstrate safety, it is necessary to understand the rates at which the gases are generated and their subsequent migration from a disposal facility after closure. This paper is concerned with modelling gas migration through a fractured higher strength host rock. A first set of simulations compares alternative approaches to modelling gas migration through a fractured rock. The approaches differ in their representation of the interaction between the fractures and the rock matrix. As expected, the gross features of many of the simulations are very similar, with a single continuum approach in which the porosity is set equal to either the fracture porosity or the matrix porosity providing the bounding cases. Gas migration is slower for those simulations where the gas can access more of the rock matrix. A final simulation, with a heterogeneous permeability field, is compared with the other simulations, again showing a very similar evolution.
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Watson, C. E., D. Savage, J. Wilson, C. Walker, and S. J. Benbow. "The long-term cement studies project: the UK contribution to model development and testing." Mineralogical Magazine 76, no. 8 (December 2012): 3445–55. http://dx.doi.org/10.1180/minmag.2012.076.8.58.
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AbstractThe international long-term cement studies (LCS) project aims to increase the understanding of the behaviour of cement within a radioactive waste disposal system and how hyper-alkaline leachates may interact with host rock. Such an understanding enables confident, robust and safety-relevant statements to be made concerning future system behaviour, irrespective of host rock, engineered barrier system, or waste type. The LCS project involves laboratory experiments, in situ tests and numerical modelling to address these issues. The agencies participating are Nagra (Switzerland), JAEA (Japan), the Nuclear Decommissioning Authority, Radioactive Waste Mangement Directorate (UK), Posiva (Finland) and SKB (Sweden).Project activities have included: the development of conceptual and theoretical models of cement–rock interaction; testing of numerical models against data from laboratory experiments and industrial and natural analogues of cement–rock reaction; and the synthesis and incorporation of performance assessment (PA) relevant data from analogue studies. Key threads running through these studies include an analysis of issues relating to upscaling of processes and data to the greater temporal and spatial scales relevant to PA, and investigations of modelling the changes in physical properties that accompany geochemical reaction. Here we present examples of the results from model test cases, highlighting the important issues that have arisen.
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Galson, D. A., and L. E. F. Bailey. "Performance assessment and the safety case: lessons from the European Commission PAMINA project." Mineralogical Magazine 76, no. 8 (December 2012): 3483–89. http://dx.doi.org/10.1180/minmag.2012.076.8.62.
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AbstractA three-year European Commission project entitled performance assessment methodologies in application to guide the development of the safety case (PAMINA) was conducted in the period 2006–2009 and brought together 27 organizations from ten European countries, including the Nuclear Decommissioning Authority and Galson Sciences Ltd from the UK. The PAMINA project had the aim of improving and developing a common understanding of performance assessment (PA) methodologies for disposal concepts for spent fuel and other long-lived radioactive wastes in a range of geological environments.Work undertaken within PAMINA focussed on four areas: (1) review of PA methodologies in participating organizations; (2) treatment of uncertainty in PA and the safety case; (3) other methodological advancements in PA; and (4) relevance of advanced PA approaches to practical cases.The state of development of a radioactive waste disposal programme has a strong influence on the type of safety case and supporting PA that is produced. A range of PA methodologies has been developed by different waste management organizations. This paper presents a selection of conclusions from the PAMINA project, in the context of general understanding developed on what would constitute an acceptable safety case for a geological disposal facility, and outlines areas for further development.
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Pransky, Joanne. "The Pransky interview: Dr Rob Buckingham, Director at UK Atomic Energy Authority and Robotics Pioneer." Industrial Robot: An International Journal 43, no. 6 (October 17, 2016): 577–82. http://dx.doi.org/10.1108/ir-08-2016-0209.
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Purpose The following article is a “Q&A interview” conducted by Joanne Pransky of Industrial Robot journal as a method to impart the combined technological, business and personal experience of a prominent, robotic industry engineer-turned successful business leader, regarding the commercialization and challenges of bringing technological inventions to market while overseeing a company. The paper aims to discuss these issues. Design/methodology/approach The interviewee is Dr Rob Buckingham, Director at UK Atomic Energy Authority (UKAEA) and Robotics Pioneer. Dr Buckingham is an innovator of snake-arm robotics for confined and hazardous environments. In this interview, Dr Buckingham shares some of his 30+ year personal and business experiences of working in industry, academia, co-founding and directing a robotics company and heading up a new UK government-funded organization for remote handling. Findings Dr Buckingham received his BSc and his MEng in the Special Engineering Programme at Brunel University in London. The program’s objective was to train engineers for the industry by developing problem-solving abilities and decision-making skills of students, which Buckingham accomplished while being sponsored by the UKAEA and as a National Engineering Scholar. After obtaining his PhD in robotics at the University of Bristol, Buckingham, he remained at Bristol for two years as a lecturer in mechanical engineering. In 1997, he co-founded OC Robotics, a private company that designs snake-arm robots specifically to operate in confined spaces. Buckingham directed OC until 2014, when he returned to where he began his early career, UKAEA Culham, this time as a Director and Head of the new Remote Applications in Challenging Environments (RACE) Centre. Under Buckingham’s leadership, RACE is involved in exploring many areas of remote operations, including inspection, maintenance and decommissioning and will be instrumental in developing new remote tools and techniques for academia and industry. Originality/value With the unique experience of studying at a university’s distinctive engineering program while working as a young engineer for the UKAEA who sponsored him, Dr Buckingham found his lifelong passion and career in robotics for remote handling. He was one of the creators of the emerging field of snake-arm robotics. He is now applying his innovative, commercial technologies and strategies from working in the nuclear, aerospace, construction and petrochemicals sectors to the industry of nuclear fusion. Dr Buckingham was awarded The Royal Academy of Engineering Silver Medal in 2009. In the same year, his company OC Robotics won the Queen’s Award for Enterprise in the category of Innovation. Buckingham is also a Fellow of the UK Institute of Engineering Technology, a Fellow of the Royal Academy of Engineering and a visiting professor at the Bristol Robotics Laboratory. He was co-chair of the Robotics and Autonomous Systems (RAS) Special Interest Group Steering Group during the preparation of the influential UK RAS strategy, which has since been adopted by UK Government.
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Walke, R. C., M. C. Thorne, and S. Norris. "Biosphere studies supporting the disposal system safety case in the UK." Mineralogical Magazine 76, no. 8 (December 2012): 3225–32. http://dx.doi.org/10.1180/minmag.2012.076.8.35.
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AbstractHigher activity radioactive wastes remain hazardous for extremely long timescales, of up to hundreds of thousands of years. Disposing of such wastes deep underground presents the internationally accepted best solution for isolating them from the surface environment on associated timescales. Geological disposal programmes need to assess potential releases from such facilities on long timescales to inform siting and design decisions and to help build confidence that they will provide an adequate degree of safety. Assessments of geological disposal include consideration of the wastes, the engineered facility, the host geology and the surface and near-surface environment including the biosphere. This paper presents an overview of recent post-closure biosphere assessment studies undertaken in support of the Nuclear Decommissioning Authority Radioactive Waste Management Directorate disposal system safety case for geological disposal of the United Kingdom's higher activity radioactive wastes. Recent biosphere studies have included: (1) ensuring that the United Kingdom's approach to consideration of the biosphere in safety case studies continues to be fit for purpose, irrespective of which site or sites are considered in the United Kingdom's geological disposal programme; (2) updating projections of global climate and sea level, together with consideration of the potential importance of transitions between climate states; (3) considering geosphere–biosphere interface issues and their representation, including redox modelling and catchment-scale hydrological modelling; and (4) identifying key radionuclides and developing a series of reports describing their behaviour in the biosphere together with an evaluation of associated implications for post-closure assessment calculations.
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Holton, D., S. Baxter, and A. R. Hoch. "Modelling coupled processes in bentonite: recent results from the UK's contribution to the Äspö EBS Task Force." Mineralogical Magazine 76, no. 8 (December 2012): 3033–43. http://dx.doi.org/10.1180/minmag.2012.076.8.19.
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AbstractA range of potential concepts for the geological disposal of high level wastes and spent fuel are being studied and considered in the UK. These include concepts that use bentonite as a buffer material around the waste containers. The bentonite will be required to fulfil certain safety functions, the most important being (1) to protect the waste containers from detrimental thermal, hydraulic, mechanical and chemical processes; and (2) to retard the release of radionuclides from any waste container that fails. The bentonite should have a low permeability and a high sorption capacity.These safety functions could be challenged by certain features, events and processes (FEPs) that may occur during the evolution of the disposal system. A consideration of how these FEPs may affect the safety functions can be used to identify and to prioritize the important areas for research on bentonite. We identify these important areas (which include hydration of compacted bentonite, illitization and erosion of bentonite), and describe how they are being investigated in current international research on bentonite.The Äspö EBS Task Force is a collaborative international project designed to carry out research on bentonite. In 2011, the Nuclear Decommissioning Authority Radioactive Waste Management Directorate joined the EBS Task Force partly to benefit from its collective experience. The work of the EBS Task Force is split into two research subareas: (1) the THM subarea, which includes tasks to understand homogenization of bentonite as it resaturates, to investigate the hydraulic interaction between bentonite and fractured rock, and to model in situ experiments; and (2) the THC subarea, which includes tasks to investigate the issue of understanding transport through bentonite, and to model in situ experiments. In particular, the bentonite rock interaction experiment is a large-scale in situ experiment concerned with understanding groundwater exchange across bentonite rock interfaces, with the objective of establishing better understanding of bentonite wetting. In this paper, we describe our work to model the spatial and temporal resaturation of bentonite buffer in a fractured host rock.
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"Launch of the Nuclear Decommissioning Authority." Nuclear Future 1, no. 3 (May 2005): 17. http://dx.doi.org/10.1680/nuen.1.3.17.66239.
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"UK Nuclear Decommissioning Authority in chaos says report." Physics Today, 2008. http://dx.doi.org/10.1063/pt.5.022494.
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"Nuclear Decommissioning Authority comments on its first year." Nuclear Energy 2, no. 4 (July 2006): 21. http://dx.doi.org/10.1680/nuen.2006.2.4.21.
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Yamana, Hajimu. "The institutional structure for decommissioning Fukushima Daiichi nuclear power plant." Annals of the ICRP, July 14, 2021, 014664532110153. http://dx.doi.org/10.1177/01466453211015396.
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This paper does not necessarily reflect the views of the International Commission on Radiological Protection. This article describes the institutional structure established for decommissioning Fukushima Daiichi nuclear power plant. To deal with the aftermath of the unprecedented nuclear accident in Fukushima, several responsible institutions such as Ministry of Economy, Trade and Industry (METI), Ministry of Education, Culture, Sports, Science and Technology (MEXT) have worked together at the initiative of the Government of Japan. In this structure, Tokyo Electric Power Company Holdings (TEPCO) implements the decommissioning due to its legal responsibility, while the essential direction and milestones are set by the Nuclear Emergency Response Headquarters of the Government of Japan. Nuclear Damage Compensation and Decommissioning Facilitation Corporation, a government-affiliated organisation, oversees and facilitates the decommissioning by TEPCO, and the Nuclear Regulatory Authority regulates safety from an independent standpoint. The main basic elements essential for the success of this long-term project have been developed, such as the technical strategy, financial system, and organisational capability. Decommissioning is making progress.
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Meehan, Dr Adam R., Dr Stephen Wilmott, Miss Glenda Crockett, and Dr Nick R. Watt. "What Will We Do With the Low Level Waste From Reactor Decommissioning?" MRS Proceedings 1107 (2008). http://dx.doi.org/10.1557/proc-1107-161.
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AbstractThe decommissioning of the UK’s Magnox reactor sites will produce large volumes of low level waste (LLW) arisings. The vast majority of this waste takes the form of concrete, building rubble and redundant plant containing relatively low levels of radioactivity. Magnox Electric Ltd (Magnox) is leading a strategic initiative funded by the Nuclear Decommissioning Authority (NDA) to explore opportunities for the disposal of such waste to suitably engineered facilities that might be located on or adjacent to the site of waste arising, if appropriate and subject to regulatory acceptance and stakeholder views. The strategic issues surrounding this initiative are described along with an update of progress with stakeholder consultations in relation to the proposed licensing of the first such facility at Hinkley Point A, which could be viewed as a test case for the development of similar disposal facilities at other nuclear sites in England and Wales.
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Broughton, David, and Michael S. Tait. "Experience in Progressing the Planning Application for New LLW Disposal Facilities for Dounreay." MRS Proceedings 1107 (2008). http://dx.doi.org/10.1557/proc-1107-43.
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AbstractAn integral part of decommissioning the Nuclear Decommissioning Agency's (NDA) Dounreay site is the management of the solid low level radioactive waste (LLW). The United Kingdom Atomic Energy Authority (UKAEA) has developed and progressed a technical and stakeholder programme that has enabled it to submit a robust Planning Application to Highland Council (HC) for New LLW Disposal Facilities at Dounreay and to submit substantive preliminary safety and environmental cases to the Nuclear Installations Inspectorate (NII) and the Scottish Environment Protection Agency (SEPA). To UKAEA’s knowledge this is the most advanced project in the UK for new LLW disposal facilities. Experience has been gained in progressing the Best Practicable Environmental Option (BPEO) Study, working with regulators in unfamiliar areas, and undertaking groundbreaking stakeholder consultation. Key lessons learnt are that stakeholders should be engaged in dialogue on the project as early as possible, documentation must be high quality and tailored to its audience, and internationally respected and credible consultants must be involved.
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Maset, Elvira Rosa. "Radioactive Waste and Spent Fuel Management in Argentina." MRS Proceedings 1475 (2012). http://dx.doi.org/10.1557/opl.2012.550.
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ABSTRACTSince its creation in 1950, the Argentine Atomic Energy Commission (CNEA), has worked on the development of applications for the peaceful use of nuclear energy. They include, among others, research and development activities in basic and nuclear technology areas, the operation of important facilities for the production of radioisotopes and the performance of tasks in connection with the nuclear fuel cycle, mining and uranium processing activities, manufacturing of fuel elements, production of heavy water and the operation of two nuclear power plants. Also demonstrating reprocessing programs have been developed.As a result of the above mentioned activities performed in the nuclear field by private and public entities, various types of radioactive waste have been and are produced during operation and maintenance of facilities and plants, and will be produced in their future decommissioning. CNEA is also responsible for the environmental remediation of the closed uranium mining and milling facilities and for the management of disused sealed sources from medical and industrial applications.Activities concerning radioactive waste management are carried on according not only to Nuclear Regulatory Authority requirements and International Atomic Energy Agency recommendations, but also to the national legal framework.The Law Nº 25.018, "Radioactive Waste Management Regime“(1998), created the National Program for Radioactive Waste Management (PNGRR), as part of CNEA organization.
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Harrison, Mike, Charlie R. Scales, Paul A. Bingham, and Russell J. Hand. "Survey of Potential Glass Compositions for the Immobilisation of the UK's Separated Plutonium Stocks." MRS Proceedings 985 (2006). http://dx.doi.org/10.1557/proc-985-0985-nn04-03.
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AbstractThe Nuclear Decommissioning Authority (NDA) has taken over ownership of the majority of the UK's separated civil plutonium stocks, which are expected to exceed 100 metric tons by 2010. Studies to technically underpin options development for the disposition of these stocks, for example by immobilization or re-use as fuel, are being carried out by Nexia Solutions on behalf of NDA. Three classes of immobilization matrices have been selected for investigation by means of previous studies and stakeholder dialogue: ceramic or crystalline wasteforms, storage MOx, and vitreous or glass-based wasteforms. This paper describes the preliminary inactive experimental program for the vitrification option, with results from a wide range of glass compositions along with conclusions on their potential use for plutonium immobilization.Following review, four glass systems were selected for preliminary investigation: borosilicate, lanthanide borosilicate, aluminosilicate and phosphate glasses. A broad survey of glass properties was completed in order to allow meaningful evaluation, e.g. glass formulation, waste loading, chemical durability, thermal properties, and viscosity. The program was divided into two parts, with silicate and phosphate glasses being investigated by Nexia Solutions and the Immobilisation Science Laboratory (ISL) at the University of Sheffield respectively.
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Harrison, Mike T., and Charlie R. Scales. "Durability of Borosilicate Glass Compositions for the Immobilisation of the UK's Separated Plutonium Stocks." MRS Proceedings 1107 (2008). http://dx.doi.org/10.1557/proc-1107-429.
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AbstractSeveral glass compositions are currently under investigation for immobilisation of the separated PuO2 that has been produced as a result of civil nuclear fuel reprocessing in the UK. Whilst a final decision on the fate of what ultimately will be over 100 tonnes of plutonium has yet to be made, all options for the disposition of this material are currently being investigated by Nexia Solutions Ltd on behalf of the Nuclear Decommissioning Authority (NDA).As one of the immobilisation options, vitrification in borosilicate glass could potentially provide a criticality-safe and stable waste form with durability suitable for long term storage and subsequent repository disposal. From an initial experimental survey of potential candidates, three borosilicate compositions were selected for a more detailed study of the waste loading and chemical durability: lanthanide borosilicate (LaBS), alkali tin silicate (ATS) and high-lanthanide alkali borosilicate (modified-MW). In these inactive tests, hafnium was used as the surrogate for plutonium. This paper describes a range of static leach tests that were undertaken in order to understand the overall durability of the waste forms, as well as the release rates of the Pusurrogate when compared to any neutrons poisons present in the glass. For the LaBS compositions it was found that the release rate of gadolinium was potentially slightly higher than that of hafnium, although both were as low as 10-5 to 10-6 g m2 day-1. The potential implications for long-term repository behaviour are discussed.
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Harrison, Mike T., and Charlie R. Scales. "Development of Borosilicate Glass Compositions for the Immobilisation of the UK's Separated Plutonium Stocks." MRS Proceedings 1107 (2008). http://dx.doi.org/10.1557/proc-1107-405.
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AbstractThe UK inventory of separated civil plutonium is expected to exceed 100 tonnes by 2010. Whilst the majority of this could be used in the manufacture of MOx (Mixed Oxide) fuel in future power generation scenarios, options for the disposal of surplus plutonium are currently being investigated by Nexia Solutions Ltd on behalf of the UK's Nuclear Decommissioning Authority (NDA). One of the options being considered is immobilisation in a durable glass matrix followed by long term storage and subsequent final repository disposal.A preliminary experimental survey assessed a selection of potential glass systems on the basis of Pu-surrogate (cerium) loading, durability, and ease of processing. Following this, a number of borosilicate compositions have been taken forward into a more detailed investigation in order to fully qualify their potential for Pu-immobilisation. The selected compositions are lanthanide borosilicate (LaBS), alkali tin silicate (ATS) and high-lanthanide alkali borosilicate (modified-MW). For this second series of experiments, hafnium was selected as the Pu surrogate, and a study of the potential waste loading as a function of temperature for the three selected compositions is described in this paper. Furthermore, several variations of the LaBS composition were fabricated in order to investigate the effect of total lanthanide content on melting temperature. The benchmark of 10 wt% HfO2 incorporation is achievable for all three glasses with temperatures of 1200, 1300 and 1400 °C required for ATS, modified-MW and LaBS respectively.