Themes and Topics

Improved techniques for the surveillance and characterisation of plant, structures, waste, land and effluents for radiological and chemical contamination. Remote field sensing for contaminated land, buildings, effluents and waste/ residue packages. Improved detectors, such as solid-state alpha cameras for more rapid analysis/more flexible deployment/improved information content.

Innovative tools and techniques which can be used to remove humans from harm, measure or estimate the radiological, chemical and physical properties of a material/ item/ waste which can be applied throughout a facility lifecycle i.e an operational plant, during Post Operational Clean Out, Deplanting and Demolition and in waste materials/packages. Approaches to ensure representative samples from heterogeneous ‘items’ and hard to reach/access areas (e.g. legacy ponds).

Specifically in the understanding of errors, accuracy and precision and in the confidence levels of ‘decision making’ and/or ‘acceptability criteria’ with respect to (correct) waste categorisation. Seeking pragmatic, implementable approaches to demonstrate confidence in decision making, which may include multiple data inputs (i.e. data fusion approaches to improve confidence).

For example, PFAs (Per- and polyfluoroalkyl compounds). There is particular interest in determining the concentrations of Persistent Organic Pollutants (POPs) in radiologically active samples.

More rapid analysis methodology to support automation, especially in labour-intensive areas of sample preparation and radionuclide separations. This is to improve analysis cost, reduce liquid waste arisings, improve turnaround time and improve supply-chain capacity. A key focus area is improved analysis/assay capabilities for alpha and beta radionuclides.

For example:

• Developments with ICPMS for elemental/radionuclide analysis either on the front end i.e. (IC-ICPMS) or other chromatographic/resin pre-treatment, or measurement e.g. ICPMS CRIS developments with protocols e.g. tandem ICPMS.
• Developments with other Mass Spec technology e.g. use of AMS to analyse very active material at high dilution.
• Photonics – development of laser technology e.g. LIBS, Raman for in-cell or glovebox analysis.
• Novel gamma spectrometry techniques e.g. software or hardware for Compton suppression or coincidence counting, new gamma detection materials or advances with imaging.
• Microfluidics or automated/semi-automated process systems – for radionuclide separation in-lab (fume cupboard/cell/glovebox) or in-situ.
• Artificial intelligence and/ or machine learning – advances in software for improvements in resolving spectra and peak stripping.
• New gaseous sensors e.g. with lower limits of detection (LOD) and ability to identify radionuclides

Improvements in existing non-destructive assay methods e.g. for fuel/fissile material content in cans and other packages. In-line, real-time materials characterisation, e.g. fuel/fissile material content of sludge during transfer/pumping operations or SNM (Special Nuclear Material) and uranic residues.

• Elemental analysis of highly active materials in sealed containers.
• Determining the contents of a concrete lined drum without opening it.

Developments in simple universal sampling tools to collect representative samples from solids, liquids or sludges that can be deployed in constrained spaces (e.g. through small apertures) or at height and potentially in high radiation areas.

This challenge explores sustainable strategies for land and groundwater remediation and the reuse of demolition arisings (inclusive of radioactive materials) to achieve a circular economy, in support of defined and achievable site end states. It includes research into opportunities and challenges, environmental impacts, and innovative remediation techniques such as biotechnology, chemical treatments, and climate-resilient solutions to ensure long-term environmental protection. Consideration should also be given to how these approaches contribute to wider environmental recovery, including ecosystem function and biodiversity outcomes across terrestrial and, where relevant, marine environments.

This challenge focuses on understanding how contaminants move, transform, and persist in the environment, and how this behaviour informs and constrains achievable site end states, particularly where these remain uncertain or unresolved. It includes research on contaminant migration, radioactive particle behaviour, and long-term environmental changes such as landscape evolution and climate change. Emphasis is placed on mechanisms like diffusion and desorption, and the development of tools to support robust environmental safety cases, including improving confidence in the long-term fate of contaminants and the ability to assert control over migrating materials in support of end state definition.

This challenge focuses on enhancing environmental decision-making by integrating life cycle analysis, and advanced qualitative and quantitative data techniques. It includes the development of tools to manage accumulative uncertainty, improve long-term environmental assessments, and apply AI and machine learning for data interpretation, automation, and historical data analysis, to support land quality and remediation efforts.

Strategies for condition management of ageing assets, including material and structural degradation (e.g. steelwork and reinforced concrete). This would include techniques for Asset Management to support and inform decommissioning strategies.

Opportunities to maximise waste segregation both at the point of generation and following retrieval. This includes approaches to reduce waste volumes (e.g. contamination in bricks), and the potential use of automated or semi-automated systems (e.g. conveyor-based sorting) across the wider NDA estate.

Reactor dismantling will generate significant quantities of irradiated Graphite waste. Research is sought into treatment methods that may reduce waste volumes and expand disposal options, including consideration of Graphite arising from spent fuel.

There are a large number of tanks, vaults, and pipework systems that are difficult to access. While bulk material can often be removed, challenges remain in efficiently removing residual heels and deposits. There is therefore a need for new techniques that enable safer, simpler, faster, and more cost effective methods for accessing and penetrating vessels and pipework (such as MSM’s (Master Slave Manipulators) while maintaining secure operations.

The NDA strategy for civil separated plutonium, following the updated UK government policy, is to immobilise the material in a stable wasteform to put it beyond reach. Work is ongoing to develop a technology option to meet this requirement. Regardless of the option developed it is expected that the immobilised waste product will be stored in a monolithic concrete store (potentially like spent fuel casks). The immobilised plutonium wasteform will be stored in interim storage until a Geological Disposal Facility is available for ultimate disposal, and it is unlikely that access to the material for continued inspection would be possible in such an arrangement.

The NDA is interested in exploring solutions to monitoring the condition of the wasteform over interim storage periods of over 30 years, to demonstrate that the wasteform has remained stable during interim storage and provide information to underpin future transport and disposal. This project should investigate in-situ techniques which could image wasteform packages within a multibarrier containment system which could comprise of meters of concrete and steel shielding but still able capture information on the condition of the wasteform within (techniques such as muon tomography could be useful). It is expected that this PhD would involve a mix of technique development and data processing algorithmics to demonstrate the condition of the material within over the multi-decade storage period.

To address the government policy for plutonium immobilisation the NDA is conducting a programme of work to investigate options for producing an immobilisation product. This will require a future manufacturing capability which will convert the ~140 tonnes of PuO2 powder into a robust stable wasteform. It is important to demonstrate that the wasteform produced meets expected specifications, and the NDA is interested in investigating techniques which could be used to characterise the product in-situ. 

This project would investigate which techniques could be used to characterise any plutonium wasteforms produced (including product density, physical properties, enrichment, chemical composition, etc) and consolidate this multisource dataset into a single source to assess against manufacturing specifications. This is expected to be a multidisciplinary project which will combine characterisation techniques with machine learning and analytics.

Sellafield Ltd will be storing SNM (Special Nuclear Material) containers for many decades until their contents can be immobilised and disposed of. Historic container populations experience a range of degradation modes such as pressurisation, mechanical damage, and corrosion. NDA are seeking non-destructive techniques for characterising the extent of these phenomena and enabling them to be tracked over time.

Pressurisation resulting from physical/chemical/nuclear processes causes SNM containers to deform and could result in container failure if allowed to progress indefinitely. These processes can be theoretically predicted, but real measurements of the extent and rate of gas generation and container deformation will provide useful validation and additional confidence. Loss of container wall thickness due to corrosion or mechanical damage may affect the structural integrity of containers or reduce the pressure they can withstand. Improved methods for quantitative measurements of these effects would enhance confidence in safe and secure storage of SNM.

Sellafield are constructing a new retreatment and repackaging facility to process historic SNM containers and produce new containers with a longer life. The new containers are constructed from 316L stainless steel and welded using Gas Tungsten Arc Welding. It is important that the microstructure and mechanical performance of the new container design are well understood. NDA are seeking an in-depth study into the effects of the manufacture and welding methods used on this container, including the phases and precipitates developed, mechanical properties, residual stresses, surface finish, and microstructure. This will inform the selection of manufacture methods, welding parameters, and surface treatments which are optimal to ensure long-term safe storage in these containers until the SNM can be immobilised and disposed of.

NDA strategy will see Spent AGR (Advanced Gas-cooled Reactor) fuel stored in fuel storage ponds for an interim period before final planned disposal in a GDF from 2075 onwards.  This will see interim storage of several decades for the fuel in wet storage.  Current monitoring approaches are based on a campaign of post storage examination where fuel is removed from pond and physically examined and routine monitoring of bulk pond water chemistry.  

The NDA is interested in exploring techniques to monitor and predict future behaviour of fuel cladding / pond infrastructure through a multi-disciplinary approach which would investigate how ROV (Remotely Operated Vehicle) and sensor advancements could be used to gather data on the physical condition of fuel in-situ during wet storage.  This should also consider how advances in AI and data analytics could be used to process the output from inspections and predict future performance.

Historically, the interaction between metallic uranium and water has been studied with a focus on the bulk metal. Methodologies have investigated the rate of corrosion of the material based upon weight differences, oxide layer growth, or volume / rate of hydrogen gas generation. Whilst these methods have been adequate to provide insight into the rate of change of the material, the quantity of radionuclides released into solution during this process have not been explored. 

There are two areas of interest related to this topic:

• Metallic U leaching: To safely dispose of these materials in a geological disposal facility, it is essential to understand the amounts and rates of radionuclide release during metallic U corrosion in water. To this end, we are interested in research to explore the leaching of metallic U, with a focus on the aqueous chemistry on the system. Ideally, aqueous chemical data will be produced in tandem with the previously established corrosion methods to identify a link between the rate at which radionuclides are released into solution, and the rate at which the bulk metal corrodes.
• Modelling release of C-14 during pond storage and disposal: Current disposal assumptions will assume that all Carbon-14 present in spent Magnox fuel will be released during disposal within a GDF.  To avoid an overly conservative approach to C-14 limits it is important to model where in the lifecycle the release of the radionuclide occurs to ensure that we can take credit for C-14 which is released during interim storage in fuel storage ponds. This project would seek to develop a modelling approach which could model the release of C-14 from uranic Magnox fuel during the lifecycle.    

A key criterion to allow spent nuclear fuel to be safely packaged for disposal is that it is conditioned such that any free moisture is limited. Residual water that is carried over in the waste container is subject to radiolysis and excess water could potentially lead to flammable atmospheres and over-pressurisation of the waste package. In principle, this should be straight-forward for spent nuclear fuels that are intact (i.e. their zircaloy or stainless-steel cladding material has not breached); however, it is much less straight-forward for failed fuels, as it is currently not possible to predict how much water remains (i.e. how much is physically/chemically entrained? how does water vapour migrate in a semi-porous, drying environment?).

Recent PhD work has looked to understand the drying processes for spent fuels from first principles [1]. Separate to this finite element-based nuclear fuel performance codes, such as BISON [2] have been developed that include modelling fission gas and material release from spent nuclear fuels in accident conditions [3]. This PhD project seeks to build on this experience by applying the fundamental modelling that can be applied to existing fuel performance codes to determine the migration of water in drying environments. 

[1] R. Ros Trujillo, Thermal Modelling of AGR Fuel Drying (ongoing project), University of Bristol, 2021–2025. 

[2] Idaho National Laboratory, BISON: https://mooseframework.inl.gov/bison/ 

[3] M.W.D. Cooper, C. Matthews, and D.A. Andersson, Development of bubble evolution model for new mechanistic transient fission gas release capability in BISON, LA-UR-23-24769, April 2023.

Understanding corrosion driven expansion under constrained conditions is critical to predicting waste package integrity. The project will investigate the fundamental mechanics of metallic fuel (e.g. Magnox and/or U) corrosion when constrained by grout and container systems. The work will focus on quantifying the relationship between constraint and expansion factor, and how forces are transmitted through the fuel–grout–container system.

Key objectives:

• Developing models linking corrosion expansion to confinement conditions
• Determining stress distribution and load transfer pathways through the encapsulation matrix
• Identifying how constraint influences corrosion behaviour and expansion magnitude
• Producing expansion vs constraint relationships for disposability assessments

The project will combine experimental data with modelling approaches to address current gaps in understanding of force distribution within encapsulated systems.

Foamed grouts could provide engineered voidage, but their mechanical behaviour under internal expansive load is not well understood. The project will investigate how foam grout is generated, structured, and how it behaves under compressive and localised loading conditions representative of uranium fuel and Magnox expansion.

Key objectives:

• Understanding foam generation mechanisms and control of void size and distribution in resultant grout formulations
• Determining how foam structure responds to applied loads, including collapse
• Identifying which foam geometries and distributions are most effective at accommodating deformation
• Developing modelling approaches to describe foam collapse and mechanical evolution

Experimental studies (e.g. controlled foam grout production and mechanical testing) will be combined with mechanistic modelling to establish structure–property relationships.

The UK has developed a range of fuels throughout its nuclear history; this includes uranium carbide fuel which is currently in storage at Dounreay.  As part of NDA strategy which will consolidate fuels for disposal it is necessary to understand how irradiated carbide fuels have evolved over time, and in addition understand how the physical condition of fuel has changed during interim storage. 

This project will seek to model the evolution of irradiated uranium carbide fuel and understand how the reactivity of the fuel alters during interim storage.  To predict how fuel would behave during transport, storage and predict changes in the reactivity of irradiated carbide fuels.

Development of optimised or innovative processes for immobilisation of radioactive wastes for storage and disposal, including use of encapsulants.  Such processes should be selected based upon candidate wastes, availability of encapsulant material (where appropriate), sustainability (including CO2 equivalent considerations), feasibility of application at full scale (including identification of secondary wastes) and compatibility of wasteform properties with waste containers and disposal concepts (including effect of evolution of wasteform properties).

Development of optimised or innovative materials for the construction of waste containers for packaging of radioactive waste for storage and disposal.  Such materials should be selected based upon candidate wasteforms, availability of material, sustainability, feasibility of application at full scale, compatibility with interim storage concepts (where applicable) and compatibility with disposal concepts (including requirements for durability of integrity).

Development of optimised or innovative techniques to monitor radioactive waste packages during interim storage.  Such techniques should be selected based upon candidate waste package types (including evolution processes to be monitored that may represent a threat to disposability), feasibility of application at full scale, compatibility with storage concepts (including prevailing levels of radiation where applicable), and feasibility of data acquisition, analysis and retention.

This research would examine how materials, water, energy, and supply chains may be affected under different climate and net zero scenarios. It would explore how resource constraints evolve over time, including changes in availability, price volatility, and environmental footprint due to climate impacts and decarbonisation pressures.

This research would explore how environmental assessment and sustainability decision-making should adapt to account for dynamic future conditions, such as shifting habitats, water availability, and ecosystem services. It would consider how to move beyond static “present-day baseline” approaches and incorporate projected future environmental states into appraisal and regulatory processes.

This research would investigate how different sustainability objectives interact, recognising that optimising for one objective (e.g. carbon reduction) may not optimise others (e.g. resource use or resilience). It would explore decision-making frameworks to identify and manage these trade-offs across engineering, planning, and operational choices.

This research would explore the use of advanced modelling and AI-enabled scenario tools to integrate climate projections, resource availability, and sustainability objectives into strategic decision-making. It could build on existing approaches (e.g. system models or carbon baselines) and extend them to support multi-factor, long-term analysis.

This research would examine how the excavated-to-waste ratio (e.g. ~25:1) drives carbon emissions, resource use, and cost in GDF (Geological Disposal Facilty) construction, and how improving this could act as a clear sustainability metric. It would explore how excavation efficiency is shaped by competing design and regulatory constraints, including thermal performance, criticality, cost, and carbon reduction. The research would develop a modelling approach to assess how design choices influence excavation volumes, and consider how advanced optimisation or AI-enabled tools could support decision-making where trade-offs are complex, enabling more robust GDF design optimisation.

Some civil decommissioning activities will require the construction of substantial infrastructure such as new intermediate storage facilities and eventual disposal facilities. Research is required into how to minimise the carbon footprint of these structures. This must be done while maintaining the necessary engineering assurance for their operational lifespan.

Creating a psychologically safe environment within complex organisations is essential for continued success, and this is further enhanced within the context of complex nuclear decommissioning activities.

The extent to which organisational members feel psychologically able to speak up, express their views and challenge the status quo can impact safety related decision making and levels of participation. Research is sought into the mechanisms involved in the creation of high levels of psychological safety and how that influences the way that individuals frame, carry out and respond to organisational requirements. (For example, carrying out safety investigations, reporting of near misses, developing a culture of innovation and the psychological safety barrier to collaboration.)

Being a ‘Learning Organisation’ informs how a business continually improves itself through using its own experiences and those of others to create its own meaningful knowledge. This is transferred across the organisation to positively impact safety and delivery performance. Further study is required into the attributes and requirements needed in order to install a strong learning organisation, specifically within the high hazard, high reliability context of nuclear decommissioning.

Having a safety culture and a results driven culture are not mutually exclusive, yet use different language, goal frameworks and behavioural requirements.

A paradox is introduced in the requirement to both maintain safety through carefulness, and conservative decision making, and also to challenge ourselves to have an increased risk appetite in order to accelerate delivery.

Within this perceived tension, what are the unique challenges faced by the workforce within a nuclear, high hazard environment to be both safe and productive, and what are the key enablers needed to deliver both, seemingly paradoxical, outcomes? How can risk be balanced in traditionally risk adverse environments.

As new delivery frameworks are being established, Supply chain use is increasing in support of delivering some of the most challenging high hazard nuclear work in the NDA estate.

Providing opportunities for Supply Chain colleagues to have a ‘voice’ in sharing ideas, actively participant in the safety culture, and sharing ideas and concerns is vital in order to ensure everyone involved in delivering the mission is ‘seen’ and ‘heard in our partnerships and joint ventures.

What are the unique challenges and unique requirements in ensuring employee voice is captured across all worker communities who contribute to achieving the mission across NDA estate, and what mechanisms should be used to capture and respond to this voice?

Explore innovative filtration techniques, including novel media for the selective removal of particulate including radionuclides from aqueous radioactive waste streams, and modelling of filtration efficacy (e.g. sand bed filters). Includes novel approaches such as the use of organic resins.

Study the application of ion exchange materials for the removal of specific radionuclides from active effluent, including optimisation of Ion Exchange performance and regeneration processes. Consider disposal implications, e.g., for streams with competing ions, bespoke pre-treatments or materials. Consider future changing streams and radionuclide demands including effluents arising from Remediation. Removal of non-radionuclides of environmental concern.

Develop sensor technologies and remote monitoring systems for real time monitoring of radioactive effluent streams, including in-line monitoring of chemical properties (pH, oxidation potential, etc.) and consider including self-monitoring/calibrating systems.

Explore by what mechanisms does the fouling of pipes arise in active effluent treatment systems and methods to remediate them. Develop novel approaches not currently used in industry. (This could include technologies, additions, knowledge and designs). Traditionally pipe fouling has been separated into two categories (1) chemical deposition and (2) biofilms. These have historically been treated as separate problems, however chemical deposition may lead to biofilm formation and vice versa and these are not fully understood currently. How do they interact?

Explore biofouling of effluent systems that cause safety and operational issues. There is an interest in research that develops understanding of biofouling prevention and solving problems caused by biofouling. This could involve control of algal blooms and similar which reduce visibility during operations, and potential for deposition of organic material in ponds.

Understand analysis and measurement techniques that could reduce the uncertainty levels in environmental permit discharge reporting. This could improve trending, prediction, and impact assessments as discharge levels reduce over time.

Investigate methods for recovering resources such as energy and water contributing to a circular economy concept.

Explore and optimise AOPs like UV, ozone etc. to enhance their efficiency in breaking down pollutants in effluent streams. The engineering of the technology has previously been a barrier to application so innovation in this area would be useful.

Explore the use of nanomaterials such as nanocomposites for targeted removal of specific pollutants enhancing the treatment efficiency.

Develop and optimise membrane separation processes such as reverse osmosis and nanofiltration for selective removal of contaminants from effluents.

Develop and optimise innovative techniques for tritium abatement.

At Sellafield site, there are alpha-contaminated environments which require decommissioning. The current baseline approach for this involves cell entries by human operators, in order to take characterisation measurements, perform decontamination operations, dismantling work, and waste handling & export. These are manually-intensive tasks with people working in Air-Fed Suits / respirators. New robotic technologies could improve on this decommissioning work – this could be via solutions which enhance the capabilities of the operator (enabling their activities to be safer), or to allow the operator to control the decommissioning from outside of the contaminated area.

This covers a range of areas but fundamentally comes down to substantiation.

Includes elements like:

• Certainty over robot positioning (e.g. where the robot thinks it is, where it wants to be and where it actually is).
• Confidence in decision making (operator out of loop, operator oversight of suggested actions, operator driven actions).
• How do we make robots that are safe around people/vulnerable items of plant (e.g. degraded gloveboxes)?
  

The introduction of robotics and AI tools into the workplace can lead to anxiety in the workforce through concerns about the lack of the requisite skills to operate them and fear of job displacement. We are interested in research that considers how best to introduce new tools into the work place, displaces fears and concerns and gives operators confidence and skill sets to make best use of the tools.

Most effective decontamination agents include complexing or chelating agents, which bond to metal ions and make them good at removing uranium/plutonium from surfaces. However, these agents also increase radionuclide mobility in a repository environment and hence raise challenges about waste stream acceptance which prevents us from using them. We are interested if there are approaches that could render these agents inactive and therefore more suitable for disposal. Robotic techniques for the application of said agents.

Potentially extension of above, linking into practically of application and removal of agents – Decontamination agents are key to allowing hands on decommissioning so there is interest in anything that supports this.

The process of moving waste materials from source to endpoint can often be highly repetitive. The logistics of moving the materials may mean that the reach of quadrupedal and tracked robotic platforms cannot reach sufficiently high to retrieve or deposit waste materials in containers. Bipedal robots with high accuracy and repeatability may hold a specific niche area in nuclear decommissioning in the future.

This research explores how construction materials from decommissioning can be integrated into a national circular economy system. It will assess how material flows could be coordinated across sectors such as construction, infrastructure, energy, and manufacturing. The study will examine the infrastructure, policy, and market mechanisms needed to enable large-scale reuse and recycling. It will identify opportunities and barriers to creating a cross-industry circular economy for decommissioning materials. The work will also evaluate environmental benefits alongside economic viability to identify practical, scalable models.

Reducing both hazard and risk are core drivers in NDA’s mission. Developing improved models to utilise the power of Artificial Intelligence (AI) in accessing, understanding and running multiple scenarios to potentially output suggestions for risk predictions is an incredible opportunity. The research may cover the data types and values of human created archived data and how AI can deeply analyse the outputs over many decades in the past. Research across many industries on how predictive analytics are being enabled would also be of great value. Also, understanding the leading AI data models and how AI can learn from other AI deployments across aligned organisations and the implications of those outputs. The outputs would also be interesting across the ever-increasing horizon scanning predictive data processing.

For projects relating to applications of artificial intelligence, please refer to and consider the sub-section entitled: “Artificial Intelligence and Other Projects Requiring Access to NDA Owned or Managed Data” under the “Additional Considerations” tab when applying to the call.

One of the impacts of policy responses to the Covid-19 pandemic has been the increased level economic uncertainty about the future. For all sectors there is a large increase in uncertainty, particularly around spending plans and revenue projections. Research into new models and how we exploit data to help show long term future risk exposures and areas for management are needed. How multiple models could be created to give various confidence level aligned outputs coupled with new analytics platforms would be of great interest. Developing new innovative quantitative models to estimate the likelihood and potential impact of long-term future risks in new ways would add great value to the planning we have in the nuclear industry which is mapping out activities over 100+ years into the future.

Artificial Intelligence (AI) is a growing topic in the nuclear sector and research into its application within NDA’s decommissioning mission requires special consideration when applying to the NDA bursary call.

• Access to NDA owned data must be identified as a risk within proposals. Applicants are expected to engage with potential sponsors to ensure that either data can be provided or that secondments into NDA group can be established to facilitate access.
• Where a secondment is required, please ensure this is correctly costed for within the proposal including travel and subsistence, security clearances and hosting/ sponsorship. Please also consider what facilities/ equipment/ software may be required as these may not be available within the NDA Group or host organisation.
• There is currently no agreed approach to regulate AI within the nuclear sector, although ONR have done some exploratory work. Applicants may wish to consider how their solution could contribute to regulator acceptance. This could include engaging publicly with organisations and regulators in nuclear.
• Applicants should consider where the PhD can go beyond the state of the art. There have been several examples where AI has either been implemented or demonstrated by consultants or the supply chain within NDA Group. It is important that any application focused on AI is aware of this research and that engagement with NDA during the call process is essential to understand this landscape.

If there are further questions on this section applicants are advised to contact nda_phd@uknnl.com who will then facilitate discussions with the appropriate sponsor within NDA group.

The NDA would welcome proposals where a PhD project would benefit from gaining access to UK research facilities for handling radioactive material. Applicants should include the estimated costs associated with undertaking R&D using radioactive materials in the proposal where a realistic estimate can be made (e.g. based on previous experience, or through discussion with the facility operator), or alternatively to state the nature and likely duration of the work they would like to undertake highlighting whether the active work would be essential to the success of the project or would just add value. If the proposed work involving radioactive materials is judged to bring significant benefits to the project, then the NDA will consider funding this work in addition to the PhD project scope. Details of the proposed active work and information about costings and/or duration can be submitted as part of the “Project Management” section in the application form.

For specific guidance, please contact nda_phd@uknnl.com.

Recognising the cross-industry similarities between the decommissioning missions of the NDA and the oil & gas and renewables community, NDA would be interested to receive research proposals that build on these synergies and address common challenges. More information on the challenges surrounding decommissioning in other sectors can be found here:

Research – The National Decommissioning Centre (ukndc.com)

Whilst this element of call has not been formulated in conjunction with the National Decommissioning Centre, any relevant proposals will be shared and assessed together with these organisations.