ATLANTIC: Accident ToLerANT fuels In reCycling

Lead Research Organisation: University of Leeds
Department Name: Chemical and Process Engineering

Abstract

ATLANTIC is a broad ranging, multi-discipline programme that will focus on the very real challenge facing the UK and worldwide nuclear industry; that of how to implement accident tolerant fuels into our existing reactor fleets.
To deliver this programme we are building on a close knit community of expertise that was created in EPSRC's PACIFIC programme and we have brought together a team of over 20 experts from 12 leading universities in the field of nuclear fission.
Our team has already established close collaborative links with EU FP7 programmes such as SACSESS and ASGARD; strengthening the breadth and depth of expertise and allowing a continuing presence on the H2020 programme GENIORS. The UK has started on NIRAB R&D programmes in fuels and recycle; which look at the future of nuclear fission for the UK. Four of the Universities contributing to these programmes are part of the ATLANTIC team.
ATLANTIC will create a foundation for implementing developmental work on ATF, but will also promote fundamental science on fuel behaviour, manufacture, separations and process kinetics.
The programme is built around five interconnected work packages focussing on the scientific and engineering challenges, with two supporting work packages that provide programme governance and create collaborative links.
Work package 1: "fuel - separations interface" will answer a number of research questions concerning the balance between recyclability and accident tolerance, particular knowledge gaps being: (1) What are the mechanisms of oxidation of ATFs under a range of conditions encountered throughout the fuel cycle but especially headend; and (2) how do the products of dissolution impact on advanced aqueous separations processes in development such as the Advanced PUREX, i-SANEX and GANEX processes. WP1 is led by Prof. Colin Boxall (Lancaster).
Work package 2: "effects of contaminants on separations" will target the GANEX and iSANEX process, investigating the effects of contaminants on speciation, e.g. Cr3+ and Np redox. WP2 is led by Prof. Laurence (Reading).
Work package 3: "investigation and optimisation of accident tolerant fuel materials" focuses on the optimisation and manufacture of accident tolerant fuel materials, and is broken down into three sub-packages: fabrication of ceramic fuels in pelletised form (U3Si2 and UN); materials characterisation and performance under lab conditions; and the effects of radiation damage on their properties and how this may modify in-reactor behaviour. WP3 is led by Prof. Karl Whittle (Liverpool).
Work package 4: "fuel behaviour, non-stoichiometry and the fuel-water interface" will build an understanding of the how these fuels react in aqueous environments in the event of pin rupture during operation and/or subsequently during long-term storage and disposal. WP4 is led by Dr. Ian Farnan (Cambridge).
Work package 5: "integrated management of accident tolerant fuels" will develop integrated separation technologies, by combining novel liquid-liquid intensified reactors and process control, which can be used in the recycling and reprocessing of metals and the production of nuclear fuel. WP5 is led by Prof. Panagiota Angeli (UCL).
Work package 6: "networking and collaboration" will provide a focal point for dissemination of the research results and to reach out to international organisations where complimentary activities can be carried out through collaboration. WP6 is led by Dr Clint Sharrad (Manchester).
Work package 7: " programme governance" will provide the necessary support to the team to ensure that the links between the work packages are effective by providing overview and advice from external experts and regular contact between team members. WP7 is led by the two principle investigators for the programme, Profs. Bruce Hanson (Leeds) and Tim Abram (Manchester).

Planned Impact

The main impact of Atlantic will be to create a greater understanding of accident tolerant fuels and cladding in relation to their manufacture, performance, handling and treatment. This body of knowledge will assist UK regulatory bodies in their understanding of the additional protection that AFTCs offer compared to current fuel and cladding technologies, smoothing the licencing process for future use in UK reactors and accelerating the switch over. The knowledge will inform UK Government strategy on future fuel cycle options. Many of the Atlantic team have had and are linked to NIRAB and will be able to feed into decisions on future government led research programmes. Prof. Robin Grimes is the Chief Scientific Officer for FCO and leads on nuclear issues across other departments, so is able to act as a direct conduit into UK Government thinking on policies. In addition, a number of the universities in the team are working with NNL on phase 1 of the BEIS funded programmes on fuels and recycle. The work on ATFC delivered in Atlantic will directly complement these national programmes and allow a better and more informed decision on the scope of future phases. Finally, the knowledge will inform industry itself on the effectiveness of ATFC in UK reactors. Our links to key industry providers such as Westinghouse (Prof. Tim Abram sits as the Westinghouse Chair in Nuclear Fuel Technology) means we will be able to provide clear and direct advice on manufacture, performance and treatment, to allow them to make more informed business decisions.
A secondary, but equally important impact of Atlantic will be to crystallise and focus UK academic effort into a targeted programme. This will provide for more effective collaboration within the UK university network and between UK universities and overseas research organisations that have similar missions. Atlantic will be a collaborative and highly expert community to nurture the careers and skills of a group of new researchers, for the benefit of all the nuclear fission community; whether academic or industrial. Atlantic will create a focal point to for a host of new collaborations that strengthen and deepen the research base across a wide range of nuclear fission topics. A number of research proposals are planned for submission to compliment Atlantic and create a wider family of researchers. Atlantic will provide, through its annual seminar, a platform for all of these researchers to share knowledge, provide assistance and collaborate.
Thirdly, Atlantic will create a group of world class researchers that can act as a team to promote and enhance UK collaborations internationally. Each of the researchers will be empowered to act as an ambassador for the UK nuclear fission community through the support of a critical mass of experts which is of equal to the other programmes around the world. We have support from the main US DoE laboratories tasked with working on fuels and separations (Oak Ridge National Laboratory and Idaho National Laboratory) that the Atlantic team will be welcomed into the US to discuss future collaborative opportunities. We have support from the key EU H2020 programmes on separations (Geniors) that similar activities will be planned.
Finally, Atlantic will deliver cutting edge research across a wide range of subjects of interest to all members of the internationally fission community.
* Fuel manufacture
* Fuel behaviour
* Spent fuel treatment
* Actinide separations
* Real time process control
* Innovative technologies
Whether through the multiple links outside of the team, or the close and effective collaboration within the team, Atlantic will create an impact far reaching and greater than the core programme.

Publications

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A. Jackson (2022) The Role of Kinetics in Advanced Nuclear Fuel Reprocessing

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Angeli P (2019) Intensified Liquid-Liquid Extraction Technologies in Small Channels: A Review in Johnson Matthey Technology Review

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Bailey D (2022) Development of monazite glass-ceramic wasteforms for the immobilisation of pyroprocessing wastes in MRS Advances

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Bailey D (2023) An Investigation of Iodovanadinite Wasteforms for the Immobilisation of Radio-Iodine and Technetium in Ceramics

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Bailey D (2021) Use of WetSEM® capsules for convenient multimodal scanning electron microscopy, energy dispersive X-ray analysis, and micro Raman spectroscopy characterisation of technetium oxides in Journal of Radioanalytical and Nuclear Chemistry

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Bascone D (2019) A modelling approach for the comparison between intensified extraction in small channels and conventional solvent extraction technologies in Chemical Engineering Science

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Berhane G (2021) The Corrosion Behaviour of High Density Fuels Under Conditions Relevant to Wet Storage & Geologic Disposal

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Berhane G. (2023) Corrosion Behaviour of Uranium Nitride Thin Films in Post-irradiation Storage in Transactions of the American Nuclear Society

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Blackburn L (2021) Review of zirconolite crystal chemistry and aqueous durability in Advances in Applied Ceramics

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Boxall C (2021) Review of dissolution and reprocessing of UN advanced technology fuels, summary of ATLANTIC project and recommendations for R&D

 
Description ATLANTIC started on the 1st December 2018 and is now complete, finishing on the 30th November 2023. Eleven of the twelve Universities on the team had already worked together on the PACIFIC (Providing A nuClear fuel cycle In the UK For Implementing Carbon reductions) programme and we welcomed the University of Liverpool as an addition to the consortium. One of the objectives of ATLANTIC was to generate new expertise into the area and so we were pleased to welcome our team of 20 Co-Is onto the project; with five new Co-Is to the area, Dr Maulik Patel (Liverpool), Dr Claire Corkhill (Sheffield), Dr Sam Murphy (Lancaster) Smith, Dr Chris Smith (Reading) and Dr Charlotte Willans (Leeds). We maintained our collaboration through our annual meetings, where we expanded the group to include many researchers from associated programmes such as AFCP fuels and recycle, who were able to present and discuss their work with us. We wanted to create a community of researchers in fuels and recycle and this has been a particular success of the programme, in that we have created a friendly space for researchers (PhD and PDRA) to present and discuss their work in detail with a large group of experts and peers from across a wide range of disciplines and backgrounds. For example, 50% of the presentations at our recent 2021 annual meeting were from researchers outside of ATLANTIC.
The programme was built around five interconnected work packages focussing on the scientific and engineering challenges, with two supporting work packages that provide programme governance, to ensure that the links between the work packages are effective and create collaborative links.
Despite the significant impact from COVID shutting University laboratories to researchers for 6 months, on average, we were able to continue with our work in the technical work packages deliver some high quality results.
In our non-technical areas, we delivered on the important activities of the programme. In WP6 (networking and collaboration), we created a new website populated with information on the programme and our recent meeting (see https://atlanticconsortium.org). In WP7 (Programme Governance) we monitored the health of the programme with 6 monthly Excomm meetings where we identified specific problems that needed correcting and continued to develop our strategy.
Work Package 1: Fuel-Separations Interface
WP1 was a collaboration between Lancaster and Leeds, with Lancaster investigating molecular scale electrochemical dissolution studies and Leeds scaling this up to fuel pellet scale.
Work at Leeds used an experimental rig for dissolution trials, commissioned in the uranics lab. Initial trials were conducted on surrogate materials (CeSi2 chips) to develop analysis methods and also characterise the baseline NOx release. A grant (provided by the NNUF) was awarded to fabricate CeSi2 and ZrSi2 pellets at Lancaster. Dissolution trials were then conducted on these pellets and the rate was found to be low, unless high temperatures and high acid strengths were used. This indicates that Si based fuels will be much more difficult to process than oxide based fuels.
Work progressed at Lancaster, building on work on UO2-based SIMFUELs, where they designed UN and U Silicide SIMFUELS and investigated their corrosion/oxidation under post-irradiation storage, head-end and disposal conditions using corrosion science-based techniques. Laboratory trials on the corrosion behaviour of CeN pellets were conducted. The pellets were cold pressed and sintered conventionally at 1500 ?C for 7 & 12 hrs, and at 1700 ?C for 12 hrs, and a set were sintered via spark plasma sinter (SPS). The pellets sintered with conventional method were observed to have disintegrated/crumbled after four hours and so there is a recommendation that sintering should be at higher temperatures and press pressures. The pellets were analysed using SEM-EDX and a CeOx 'crust' was found to be covering pellet, with some high nitrogen areas located in amongst curst. XRD revealed some crystalline CeN signal, but it was likely buried beneath layer of surface amorphous oxide.
Whilst the UN SIMFUELS are being fabricated in Lancaster's new National Nuclear User Facility, UTGARD Lab, experimental studies have progressed on U Silicides as well. A methodology was developed using SPS to fabricate pellets of U3Si2.
Work Package 2: Effects of Contaminants on Separations
WP2 was a collaboration between Manchester, Oxford and Reading, where the kinetically transient systems of ligand behaviour in the extraction process was spectroscopically (Oxford and Manchester) and by computation (Reading).
Work at Reading synthesised and tested a number of target ligands. The first set of ligands Ph4-BTP, Ph4-BTBP and Ph4-BTPhen were manufactured and their solubility tested in a series of diluents; Octanol, Cyclohexanone, DCM, MeCN and DMSO. Unfortunately, for a number of the diluents solubility was found to be poor and so alternatives are being investigated.
Work Package 3: Investigation and Optimization of Accident Tolerant Fuel Materials
WP3 was a collaboration between Liverpool, Manchester and Sheffield; with Manchester and Sheffield studying the manufacture and characterisation of UN and U3Si2 ceramic fuels and Liverpool studying the impacts arising from radiation damage. Linked with this work, at Liverpool, samples of Zircaloy-4, Ti2AlC, NbTiAlC and SiC were tested in high temperature steam (up to 1100ºC) to replicate a Loss Of Coolant Accident (LOCA). The samples were tested to examine coating options, with the results examined by XRD, SEM and TEM. A 3.5 Yr Ph.D position was created on "Atomic level understanding of radiation effects in next generation nuclear fuels using advanced electron microscopy and x-ray scattering techniques"; funded through the school of engineering at Liverpool. The student was co-supervised by Dr. Ross Springell from Bristol, where samples will be fabricated for irradiation experiments at the Dalton Cumbrian Facility (DCF); and performing post irradiation characterisation at Liverpool.
Researchers at the Nuclear Fuel Centre of Excellence (NFCE) at the University of Manchester investigated the manufacturability and operability of the high density nuclear fuel U3Si2, particularly considering reactions with oxygen and water vapour which could occur at multiple stages through the lifecycle of a nuclear fuel. Oxidation studies inform the behaviour and product quality during manufacturing and storage, whilst water reactivity studies inform in-reactor exposure by fuel pin leakage and long-term storage. This work generated a lot of interest and has led to several complementary studies with collaborators, including 1 PhD student, 3 PDRAs and 6 senior researchers, as well as multiple presentations to international audiences. Additionally, the pursuit of synchrotron techniques at the Diamond Light Source has led to the collaborative development of containment methods for experiments with radioactive materials. There were several prominent findings thus far, and investigations are ongoing in collaboration with AFCP, including temperatures and heat loads of rapid self-sustained reactions with oxygen, which inform accident scenarios and the experimental and theoretical terminal mass gains of reaction do not agree, which are thought to be due to unreacted Si (identified by TEM). Also observations of U3Si2 passivation with time, which could affect safety and sinterability, show approximately parabolic behaviour which informs how the material will perform over sustained exposure to a reactant; and U3Si2 powder shows similar initial reactivity in both synthetic air and water vapour environments.
At Sheffield, research addressed the key challenge of developing a reliable and scaleable route to the synthesis of uranium (VI) nitride as the feedstock for UN nuclear fuels, by high temperature ammobolysis, through a new NH4UF8 precursor. This route will enable the simple approach of transition metal doped UN fuels. We developed new mechanistic understanding of the synthesis of nitrides through reaction of oxide and chloride compounds with NaNH2; leading to the discovery of room temperature synthesis of UN2 from reaction between UCl4 and NaNH2. This established a new collaboration with Prof. Yuji Masubuchi at Hokkaido University. Considering the application of this method to the synthesis of UN2 from uranium oxides, DFT calculations indicated only a marginally positive enthalpy for the following reaction, suggesting potential feasibility within the margin of uncertainty of such estimates:
UO3 + 2 NaNH2 ? UN2 + 2 NaOH + H2O ?Hcalc = 0.061 eV (6 kJ mol-1)
In fact no uranium nitride products were obtained, the products were determined to be more reduced uranium oxide, as supported by XPS analysis undertaken in collaboration with project partners at The University of Manchester, using equipment within the Royce Institute. In the case of UO2+x, we established that reaction in molten NaNH2, leads to reduction to stoichiometric UO2.00, this work led to a publication in the Journal of Nuclear Materials.
Work Package 4: Fuel Behaviour: non-stoichiometry and the fuel-water interface
WP4 was a collaboration between Bristol, Cambridge and Imperial. Cambridge and Imperial combined electronic structure and empirical potential to address non-stoichiometry and homogeneity in the candidate fuels and Bristol studied water interactions at a fundamental level.
At Bristol, work was on the synthesis, oxidation and dissolution of uranium silicide phases and investigating the effects of additives on uranium nitride behaviour, specifically, poly-epitaxial and single crystal thin films of UN and U2N3. This led to the fabrication and testing of uranium nitride thin films, as these are an excellent representation of a material surface and a perfect candidate to study surface processes. One area of study was the investigation of the effect of dopants on the structures, specifically niobium. The U nitride films were first fabricated with reactive sputtering in N2 and co-sputtering with a varied dopant gun power to make polycrystalline films. This technique is proven as a single crystal [0 0 1] UN and a-U2N3 films has been previously grown in Bristol. Analysis using XRD of the resulting film, showed 5 % Nb has both UO2 and UN peaks and UN peaks shift from 33 - 36 2? degrees. Further work will be done on chemical characterization using X-ray Photoelectron Spectroscopy (XPS), Scanning Electron Microscopy (SEM) - EDX) and Transmission Electron Microscopy (TEM).
At Cambridge a series of high-resolution imaging, chemical mapping and spectroscopy techniques was applied to leached and unleached, oriented thin films of UO2 under anoxic conditions; these provided a good representation of a specific surface of UO2. Further to this work (completed in the first half of the programme) a study on ab-initio random structure searching to improve fabrication routes for U3Si2 and UN fuels has commenced. The study is using a CALYPSO structure prediction with DFT and DFT+U (based on Noordhoek et al. (2016) J. Nucl. Mater. 479 216) that compares U = 0 eV calculations, and U = 1.5 eV calculations separately. In addition, there will be USPEX structure prediction using DFT+U (based on Lopes et al. (2018) J. Nucl. Mater. 510 331) that uses only U = 1.5 eV 11. A complete full U-Si binary system with RSCAN will be done, that introduces pressure into system to explore fabrication routes.
Work Package 5: Integrated management of accident tolerant fuels
WP5 was a collaboration between Edinburgh and UCL; with Edinburgh studying process control by the development of real time sensors and UCL developing integrated separation technologies which can be used in the recycling of nuclear fuel.
At the University of Edinburgh, microchannels with multiple inlets (Figure 5 left) and integrated micro electrode array sensors designed, following discussion with UCL. These used a combination of semi-conductor manufacturing techniques and acid resistant silicone-based polymers.
The purpose of these sensors was the provision of real-time data on the metal ion extraction process as a function of distance (time) along the flow channel. These designs of electrochemical sensors were demonstrated to be capable of selectively and quantifiably measuring specific nitric acid decomposition products such as local nitrite along with dissolved oxygen, free metal ions and the local pH. In a stagnant environment, the sensor performance has been investigated using the model system of Fe(III), with -SO3-Ph-BTBP, as a model extraction ligand, in nitric acid. It was shown that the sensors can quantitatively measure the presence of both dissolved and complexed Fe(III) (below).
At UCL two intensified contactors were developed for liquid-liquid extraction separations based on small channels. In one approach the two liquid phases join in a channel of mm scale and form orderly flow patterns which enhance mass transfer. The sizes of the channels can be up to a few mm, enabling flowrates up to 30 ml/min. In the other approach the two phases joined at high velocities as jets in a mm scale channel, forming dispersions with narrow size distribution (flowrates up to 70 ml/min, Figure 6 right). In both cases high extraction efficiencies and mass transfer coefficients (applied to the separation from nitric acid solutions of mixtures of Eu, Er and Eu) were found while it was possible to operate with pure TBP as the organic phase.
The availability of real-time sensor readings, providing concentration measurements, opens up the possibility of monitoring and control of separation processes. Work was focused on the development of short-cut models which formed the basis of a model-based control methodology. The models were used to determine correcting changes in solvent and extractant flow rates to address the effects of changes (concentrations, flow rates) in upstream process steps. Comparison of electrochemical experiments with this theory enabled model validation.
Exploitation Route The link between ATLANTIC and the BEIS Advanced Fuel Cycle Programme was very strong and the programme benefitted a great deal from the expansion in the number of AFCP projects that linked directly or complement ours. The following was a set of examples of projects funded by AFCP that fit within the sphere of interest for ATLANTIC.
• In WP1 Ghebrehiwot Berhane a PDRA at Lancaster studied UN Fuel Inventory at Higher Burnups Using FISPIN. Computations were conducted to calculate the fission product inventories of UN fuels at, inter alia, 40 and 60 GWd/tU burnup in a PWR reactor. In parallel, Dr Berhane conducted experimental studies of the corrosion of cerium silicides and nitrides as UN surrogates.
• In WP3 there were dedicated collaboration meetings between University of Manchester NFCE and University of Bristol, as the comparison between bulk scale oxidation testing and thin film corrosion studies complement each other well.
• In WP3 a PhD position on "Atomic level understanding of radiation effects in next generation nuclear fuels using advanced electron microscopy and x-ray scattering techniques" was been funded by Liverpool.
• In WP4 Lottie Harding a PhD researcher Bristol studied Advanced technology fuels and the characterisation and oxidation of uranium silicide phases. In addition, Conor Galvin a PhD researcher at Imperial is studying atomic scale modelling of UN fuel.
Beyond AFCP, research projects were linked into ATLANTIC, bringing in funding from other sources. Some examples were:
• Jade Li a PhD researcher at Lancaster is funded by the Leverhulme Trust and is studying diffusion in non-stoichiometric uranium nitride
• Julio Vacquez-Chavez a PhD researcher funded by Leeds who studied voloxidation of fuels.
• National Nuclear Laboratory, £150k cash contribution to support ATLANTIC PDRA Dr G. Berhane during the first of three years on the project; and
o Additional supervisory input from Prof. C. Degueldre in the area of fission product speciation within spent ATFs.
• Westinghouse Sweden - in kind expertise on ATF pellet preparation by field-assisted rapid sintering.
• The Leverhulme Trust - £100k cash contribution to support PhD student Jade Li
• University of Leeds - cash contribution of £80k to support PhD student Julio Vazquez-Chavez
• Lancaster University - cash contributions of:
• £100k to support PhD student Nicola Zagni; and
• £12.4k to part-support purchase of a glove box add-on for spark plasma sintering equipment
Within the ATLANTIC Project we established new collaborative partnerships, for example one between Sheffield and Manchester, for N determination by XPS analysis of the products of ammonolysis and NaNH2 reactions. Through video conferencing the procedure for preparation and packaging of the samples to the XPS facility within the Royce Institute at Manchester was agreed. The data supported at least one future joint publication between the two research groups.
More widely, the members of ATLANTIC collaborated with the National Synchrotron Light Source II, Brookhaven National Laboratory, to develop a remote access mechanism for X-ray Absorption Spectroscopy studies. A successful test experiment was completed in December 2020 by Sheffield (the first such experiment at the NSLS II synchrotron), with the project team undertaking data acquisition in real time on beamline BMM, utilising a pre-fabricated sample array mailed in to the facility. This successful test experiment will enable us to undertake planned XAS studies of transition metal environments in UN2 / UN in the next stage of the project, without the need to attend in person and will benefit the whole ATLANTIC project, as well as other researchers that utilise the BMM beamline.
The ATLANTIC programme enabled PhD students and PDRA staff at Bristol to develop much closer links to other research groups across the UK that have common/complementary goals. More specifically, since the start of the programme, together with members of the nuclear fuels group at the University of Manchester, we set up an early career collaborative team of PDRAs, fellows, and students. This was an extremely useful forum, which brought together colleagues at other institutes, in different disciplines, working at different length scales, towards a common goal - namely the investigation and improvement of advanced technology fuels.
One of the greatest challenges for many of the institutes involved in the fuel development themes within ATLANTIC was being able to work with good quality stocks of uranium metals and compounds for fuel synthesis and characterisation. Within this programme we were able to exchange material between institutes to push forward work packages. We collaborated on analysis of photoemission spectroscopy and x-ray diffraction data, essential for identification of phase structures and chemistry.
Together with the AFCP we brought academics from outside the original ATALNTIC team, such as Dr. Simon Middleburgh and colleagues at the university of Bangor, who have a wealth of experience and contacts on the subject of ATF.
Sectors Energy
 
Description Investigators on ATLANTIC have been appointed to important advisory roles by the Secretary of State for Business, Energy and Industrial Strategy. Hanson, Mount (Chair) and Sharrad are members of the Molten Salt Advisory Group, convened by BEIS to provide technical advice on how to most effectively leverage UK capability to support the development and exploitation of molten salt technologies. Hyatt and Corkhill were appointed to HM Government's Committee on Radioactive Waste Management in 2019, providing expert advice on the storage, treatment and disposal of used nuclear fuels and radioactive wastes. In this role, they engage directly with policy makers and Hyatt has provided evidence to the House of Commons BEIS Select Committee inquiry on the Draft National Policy statement for Geological Disposal Infrastructure.
First Year Of Impact 2019
Sector Energy
Impact Types Policy & public services
 
Description Appointed to the HM Treasury Green Taxonomy Energy Working Group
Geographic Reach National 
Policy Influence Type Membership of a guideline committee
 
Description IChemE Community of Practice on Energy - Management Committee
Geographic Reach National 
Policy Influence Type Membership of a guideline committee
URL https://www.icheme.org/membership/communities/communities-of-practice/
 
Description Member HM Goverment Committee on Radioactive Waste Management
Geographic Reach National 
Policy Influence Type Membership of a guideline committee
 
Description Molten Salts Advisory Group
Geographic Reach National 
Policy Influence Type Participation in a guidance/advisory committee
URL https://www.gov.uk/government/publications/advanced-nuclear-technologies/advanced-nuclear-technologi...
 
Description ANZAC@ANSIC: Advanced Technology Fuels in support of Net Zero And DeCarbonisation
Amount £65,000 (GBP)
Funding ID GC-516 
Organisation National Nuclear Laboratory 
Sector Public
Country United Kingdom
Start 11/2021 
End 03/2022
 
Description ATLANTIC: Accident ToLerANT fuels In reCycling
Amount £2,545,630 (GBP)
Funding ID EP/S011935/1 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 12/2018 
End 11/2023
 
Description Advanced Fuel Cycle Programme - Advanced glass formulations
Amount £89,468 (GBP)
Organisation Department for Business, Energy & Industrial Strategy 
Sector Public
Country United Kingdom
Start 09/2020 
End 04/2021
 
Description Advanced Fuel Cycle Programme - phase 2
Amount £250,000 (GBP)
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 03/2020 
End 03/2021
 
Description Advanced Nuclear Fuels Programme
Amount £129,291 (GBP)
Funding ID NNL/NIPO/037 
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 06/2020 
End 06/2021
 
Description Advanced Nuclear Fuels Programme
Amount £750,000 (GBP)
Funding ID NNL/NIP/003 
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 09/2019 
End 06/2021
 
Description Advanced Nuclear Fuels Programme
Amount £810,000 (GBP)
Funding ID NNL/NIP/003 
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 09/2019 
End 10/2021
 
Description Disposal MOX fabrication and characterisation
Amount £250,000 (GBP)
Organisation Nuclear Decommissioning Authority NDA 
Sector Public
Country United Kingdom
Start 11/2020 
End 09/2021
 
Description GENIORS (Gen IV integrated oxide fuels recycling strategies)
Amount € 6,000,000 (EUR)
Funding ID 755171 
Organisation FP2020 
Sector Charity/Non Profit
Country United States
Start 05/2017 
End 05/2021
 
Description Game Changers
Amount £76,994 (GBP)
Funding ID GC-392 
Organisation National Nuclear Laboratory 
Sector Public
Country United Kingdom
Start 09/2021 
End 03/2022
 
Description NNL Advanced Nuclear Fuels Programme - Spent Fuel Management
Amount £150,000 (GBP)
Funding ID NNL/NIP/0019 
Organisation National Nuclear Laboratory 
Sector Public
Country United Kingdom
Start 01/2020 
End 06/2021
 
Description NNUF2a: Facility for Radioactive Materials Surfaces (FaRMS)
Amount £922,271 (GBP)
Funding ID EP/V035495/1 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 09/2021 
End 09/2024
 
Description Platform for Long-term Experimental Investigation of Alteration in Disposal Environments and Storage - PLEIADES
Amount £597,980 (GBP)
Funding ID EP/V035215/1 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 09/2021 
End 09/2023
 
Description Production of Uranium Oxycarbide Kernels for use in the Development of UK Coated Particle Fuel
Amount £50,000 (GBP)
Funding ID EP/X525583/1 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 03/2023 
End 12/2023
 
Description Production of Uranium Oxycarbide Kernels for use in the Development of UK Coated Particle Fuel
Amount £91,000 (GBP)
Funding ID NNL/NIP/0079 
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 11/2022 
End 03/2023
 
Description The electrochemistry of Ag(II) and its application in spent fuel dissolution
Amount £60,000 (GBP)
Funding ID NNL/UA/167 
Organisation National Nuclear Laboratory 
Sector Public
Country United Kingdom
Start 09/2022 
End 09/2026
 
Description UK Government/Department of BEIS Nuclear Innovation Programme (NNL/NIP/002) Advanced Fuel Cycle Programme - Fuel (Aqueous Recycle)
Amount £757,946 (GBP)
Funding ID NNL/NIP/002 
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 12/2019 
End 03/2021
 
Description UTGARD Lab - 5 User Access Awards
Amount £7,511,247 (GBP)
Funding ID EP/T011351/1 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 03/2019 
End 03/2024
 
Title A Statistical Model of High Burnup Spent Nuclear Fuel Compositions and Decay Heats 
Description We have developed a flexible model for predicting spent nuclear fuel (SNF) isotopic and elemental compositions and their decay heats for high-burnup fuel of pressurised water nuclear reactor systems. The approach uses a statistical based to predict SNF compositions which has been tested against established compositions data and can readily extrapolate to predict SNF compositions beyond established reactor conditions. This model is highly adaptable and modular, with functionality able to be added or removed as the user requires. This was developed entirely in accessible software (MS Excel), and is independent of proprietary codes (e.g. FISPIN, SERPENT, ORIGEN, etc) which fulfil the same purpose, but require costly licensing, high computational requirements, and a knowledge of programming beyond that of most experimental researchers. This allows the calculation of fuel discharge compositions (i.e. at removal from a reactor), and can then predict fuel compositions and decay hears using the known radioactive decay of fission products and actinides. This work has been published as a preprint and is present undergoing peer review at the time of writing, and has been presented at EPSRC project meetings (ATLANTIC). 
Type Of Material Improvements to research infrastructure 
Year Produced 2021 
Provided To Others? Yes  
Impact Currently the publication of this model is undergoing peer review. No notable impacts as of yet. 
URL https://www.preprints.org/manuscript/202011.0182
 
Title Densitometer for radioactive liquids 
Description Density measurements can be performed for various liquids (aqueous and organic) at controlled temperatures up to 80 deg. C using low sample volumes. Samples that contain radioactive materials to support solvent extraction of spent nuclear fuel research can be readily measured in accordance with the safety protocols that have been developed for this work. 
Type Of Material Improvements to research infrastructure 
Year Produced 2019 
Provided To Others? No  
Impact Interest for those in the aqueous recycle community to provide or share data from the use of this instrument. 
 
Title Interfacial tension 
Description A bespoke instrument has been developed that utilises the pendant drop method to provide interfacial tension measurements for liquid-liquid interfaces such as those used in the solvent extraction of spent nuclear fuel. The instrument provides control of the droplet formation and can take the high resolution images of the droplet that can then be used to determine the interfacial tension. The instrument provides temperature control and can readily accommodate radioactive samples. The instrument is deliberately designed for the possibility that this may be used for highly radioactive samples where a glovebox or containment box is required. 
Type Of Material Improvements to research infrastructure 
Year Produced 2020 
Provided To Others? No  
Impact Interest for those in the aqueous recycle community to provide or share data from the use of this instrument. 
 
Title Stirred-Reactor Coupon Analysis test 
Description Previously in the nuclear waste performance community, the single-pass flow-through (SPFT) method ASTM C1662 (e.g., ASTM C1662-18 2018) has been the most common test chosen to evaluate waste form corrosion in dilute conditions. The test method consists of a target solution passed at a relatively low flow rate over a sample material (usually in particle form) and measuring the composition of the effluent by solution analyses. The typical analytical techniques for solution analyses have detection limits that can require lowering flow rates (and thus decreasing the dilution of the contacting solution) just so the concentration of ions in the resultant sample is high enough to measure. This higher concentration impacts the resultant measured rate to the extent that extrapolations of multiple measurements must be made to estimate the dissolution rate in infinitely dilute conditions. A new technique, termed the stirred-reactor coupon analysis (SRCA) method, has been developed to achieve solution dilution through a large, well-mixed volume rather than via solute flow. In this method, monolithic glass coupons are masked with an inert material before undergoing corrosion in a large volume of solution with known chemistry and temperature for a pre-determined duration. After terminating the test, the mask is removed and the step height difference between the protected and corroded portions of the sample coupon is measured to determine the extent of glass dissolution. The step height can be converted to a rate measurement using the test duration and glass density. 
Type Of Material Improvements to research infrastructure 
Year Produced 2022 
Provided To Others? No  
Impact The method will be developed into an ASTM standard for application to understanding the durability of radioactive waste in geological disposal environments. 
 
Title Viscometer for radioactive liquids 
Description Viscosity measurements can be performed for various liquids (aqueous and organic) at controlled temperatures up to 80 deg. C. An attachment has been included that allows the use of low sample volumes which can be retrieved if neccessary as it is a non-destructive method. Samples that contain radioactive materials to support solvent extraction of spent nuclear fuel research can be readily measured in accordance with the safety protocols that have been developed for this work. 
Type Of Material Improvements to research infrastructure 
Year Produced 2020 
Provided To Others? No  
Impact Interest for those in the aqueous recycle community to provide or share data from the use of this instrument. 
 
Description Collaboration with China Nuclear Power Technology Research Institute. 
Organisation China General Nuclear Power Group
Department China Nuclear Power Technology Research Institute
Country China 
Sector Private 
PI Contribution A collaboration has been established with the Accident Tolerant Fuels research group of the China Nuclear Power Technology Research Institute, focused on the basic science of accident tolerant nuclear fuel cladding performance. The UK partners will investigate the high temperature stability and corrosion behaviour using materials manufactured by the partner, in particular using surface sensitive spectroscopy techniques. The UK team plans to host an early career researcher from the partner to facilitate joint research. The UK team will also contribute to development of joint publications which will be publicly available through open access in a peer reviewed journal.
Collaborator Contribution The Accident Tolerant Fuels research group of the China Nuclear Power Technology Research Institute, will provide samples of candidate accident tolerant nuclear fuels manufactured by different methods for characterization by the UK partner. Additionally the partner organisation plans to second an early career researcher to the UK team to facilitate joint research. The partner organisation will also contribute to development of joint publications which will be publicly available through open access in a peer reviewed journal.
Impact The collaboration is between leading materials science research groups in the UK and China and is at an early stage, hence no publications or outputs to date.
Start Year 2019
 
Description Collaboration with High-tech Ceramic Advanced Manufacturing Technology, Guangdong University of Technology. 
Organisation Guangdong University of Technology
Country China 
Sector Academic/University 
PI Contribution A collaboration has been established with the Center for High-tech Ceramic Advanced Manufacturing Technology, Guangdong University of Technology, focused on the basic science of accident tolerant nuclear fuel cladding performance. The UK partners will investigate the high temperature stability and corrosion behaviour using materials manufactured by the partner, in particular using surface sensitive spectroscopy techniques. The UK team plans to host an early career researcher from the partner to facilitate joint research. The UK team will also contribute to development of joint publications which will be publicly available through open access in a peer reviewed journal.
Collaborator Contribution The Center High-tech Ceramic Advanced Manufacturing Technology, Guangdong University of Technology, will provide samples of candidate accident tolerant nuclear fuels manufactured by different methods for characteisation by the UK partner. Additionally the partner organisation plans to second an early career researcher to the UK team to facilitate joint research. The partner organisation will also contribute to development of joint publications which will be publicly available through open access in a peer reviewed journal.
Impact The collaboration is between leading materials science research groups in the UK and China and is at an early stage, hence no publications or outputs to date.
Start Year 2019
 
Description Collaboration with Idaho National Laboratory 
Organisation Idaho National Laboratory
Country United States 
Sector Public 
PI Contribution Postdoctoral staff time for sample generation and subsequent analysis of phases exploring the impact of radiation effects (Co-60 gamma irradiation) on the distribution of uranium and a selection of problematic fission products in PUREX separations in order to understand whether high burn up fuels can be readily recycled in established separations processes and, if so, under what conditions.
Collaborator Contribution Partners provided training, access to materials and Co-60 irradiator access to allow the gamma irradiation of uranium containing samples.
Impact Aqueous phase analysis indicates varied trends in U distribution with dose, formation of Zr containing precipitates with dose and increases in organic phase viscosity has been observed at elevated dose. Organic phase analysis will be performed in order to definitively confirm element distribution behaviour and various physicochemical parameters of these samples will be determined to understand how irradiation dose effects bulk phase behaviour. This collaboration is multidisciplinary across chemical engineering, chemistry (organic, inorganic and physical) and radiation science.
Start Year 2018
 
Description Collaboration with Idaho National Laboratory 
Organisation Idaho National Laboratory
Country United States 
Sector Public 
PI Contribution Expertise in nuclear materials synthesis - thin films of UO2 and U-silicide, U-nitride. Two students spent three months each at INL facilities.
Collaborator Contribution Provided plasma-FIB and PPMS measurement facilities.
Impact Student training. Thermal conductivity measurements on nuclear fuel surfaces.
Start Year 2019
 
Description Collaboration with Laboratory of Structural Inorganic Chemistry, Hokkaido University 
Organisation Hokkaido University
Country Japan 
Sector Academic/University 
PI Contribution A collaboration has been established with the Laboratory of Structural Inorganic Chemistry, Hokkaido University, Japan, focused on the basic science of soft chemical synthesis of nitride compounds, relevant to accident tolerant nuclear fuels. The UK partners are investigating the mechanisms of soft chemical synthesis of metal nitrides and characterisation of the products. The UK team will also contribute to development of joint publications which will be publicly available through open access in a peer reviewed journal.
Collaborator Contribution The Laboratory of Structural Inorganic Chemistry, Hokkaido University, Japan, has provided expertise in the conventional synthesis of metal nitrides by ammonolysis and the analytical determination of N and O content on samples provided by the UK team. The Japan partner also hosted a UK researcher for one week to undertake practical training in ammonolysis synthesis. The partner organisation will also contribute to development of joint publications which will be publicly available through open access in a peer reviewed journal.
Impact The collaboration is multidisciplinary between leading materials science and chemistry research groups in the UK and Japan and is at an early stage, the first joint publication is in process.
Start Year 2019
 
Description Washington State University at Pullman 
Organisation Washington State University
Country United States 
Sector Academic/University 
PI Contribution Investigation and understanding of phase separation and crystallisation in glass-ceramics for immobilisation of high level radioactive waste from future fuel cycles.
Collaborator Contribution Investigation and understanding of phase separation and crystallisation in glass-ceramics for immobilisation of high level radioactive waste from future fuel cycles.
Impact See publications section.
Start Year 2015
 
Description 12 Monthly Meetings with NNL - Accident Tolerant Fuels 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact 12 monthly meetings with NNL to discuss progress with Accident Tolerant Fuel Project
Year(s) Of Engagement Activity 2020,2021
 
Description ATLANTIC 2nd Annual meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact The 2nd ATLANTIC annual meeting was held over 20th - 21st January 2021 as a virtual event. Over 40 participants heard about the latest research and developments in Advanced Technology Fuels being undertaken by project and associated partners. The presentations stimulated much discussion and suggestions for further work
Year(s) Of Engagement Activity 2020
 
Description ATLANTIC Annual Meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact Annual meeting of ATLANTIC Consortium. Presentations made on progress in all themes. Held on line on 20-21 Jan 2021
Year(s) Of Engagement Activity 2021
 
Description ATLANTIC Annual meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact The 1st Annual meeting of the Atlantic Consortium took place over two days at the Imperial War Museum North in Manchester on the 21st & 22nd January 2020. Professor Bruce Hanson (PI of ATLANTIC) opened the proceedings by giving a general overview of the research programme. Presentations from ATLANTIC researchers, researchers working on related projects and the National Nuclear Laboratory generated much discussion, exchange of ideas and plans for further work.
Year(s) Of Engagement Activity 2020
 
Description ATLANTIC EXCOMM 
Form Of Engagement Activity A formal working group, expert panel or dialogue
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact July 2020 meeting of ATLANTIC Consortium Executive Committee
Year(s) Of Engagement Activity 2020
 
Description ATLANTIC EXEC MEETING - LEEDS May 2019 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact meeting of the ATLANTIC project exec team with NNL
Year(s) Of Engagement Activity 2019
 
Description ATLANTIC Kickoff meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact The ATLANTIC consortium held its kick-off meeting on Wednesday 16th January 2019 at the University of Leeds.

Academic researchers presented overviews of the various work packages within the research programme and outlined plans going forward
Year(s) Of Engagement Activity 2019
 
Description ATLANTIC Meeting, Manchester Jan 2020 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact ATLANTIC Annual Progress meeting
Year(s) Of Engagement Activity 2020
 
Description Atlantic annual meeting 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact Annual consortium meeting of the Atlantic project
Year(s) Of Engagement Activity 2019,2020
 
Description BBC 
Form Of Engagement Activity A broadcast e.g. TV/radio/film/podcast (other than news/press)
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Public/other audiences
Results and Impact Prof. Claire Corkhill was interviewed on the BBC Radio 4 PM Programme on the radiation leak and situation at the Taishan nuclear power plant, in China, of the EPR design.
Year(s) Of Engagement Activity 2021
 
Description BBC 5 Live / BBC Cambridge / The Naked Scientists podcast 
Form Of Engagement Activity A broadcast e.g. TV/radio/film/podcast (other than news/press)
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Public/other audiences
Results and Impact Interviewed for BBC Radio Cambridge and the Naked Scientists podcast on radioactive waste disposal.
Year(s) Of Engagement Activity 2020
URL https://twitter.com/NakedScientists/status/1246857392463269888
 
Description BBC Inside Science 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact Interviewed on BBC Inside Science about radioactive waste disposal, radioactive waste from fusion energy and Fukushima Daiichi clean up-related research.
Year(s) Of Engagement Activity 2022
URL https://www.bbc.co.uk/sounds/play/m0013zm3
 
Description BBC World Service - nuclear fuel removal 
Form Of Engagement Activity A broadcast e.g. TV/radio/film/podcast (other than news/press)
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact Interviewed by Ritulah Shah on BBC World Service News Hour programme, to discuss the removal of nuclear fuel from the Fukushima Daiichi nuclear power plant.
Year(s) Of Engagement Activity 2019
URL https://www.bbc.co.uk/news/world-asia-47933031
 
Description Bimonthly meetings with Westinghouse Sweden to discuss advanced sintering techniques for accident tolerant fuels 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact Beginning September 2020, bimonthly meetings with Westinghouse Sweden to discuss advanced sintering techniques for accident tolerant fuels
Year(s) Of Engagement Activity 2020,2021
 
Description CNN breaking story: Taishan nuclear power plant. 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Public/other audiences
Results and Impact Professor Neil Hyatt Neil Hyatt was interviewed by CNN about the reported leak of radioactivity at the Taishan nuclear power plant in China.
Year(s) Of Engagement Activity 2021
URL https://twitter.com/i/status/1405429331942379520
 
Description CNN interview - Fukushima contaminated water release 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Public/other audiences
Results and Impact Gave CNN interview on the topic of radioactive water stored at the Fukushima site.
Year(s) Of Engagement Activity 2020
URL https://edition.cnn.com/2020/10/24/asia/japan-fukushima-waste-ocean-intl-scli/index.html
 
Description CoRWM presentation at NDA Integrated Waste Management Programme Stakeholder Workshop 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact Gave a talk on behalf of the Committee on Radioactive Waste Management at the Nuclear Decommissioning Authority's Integrated Waste Management Programme Stakeholder Workshop.
Year(s) Of Engagement Activity 2020
URL https://www.marickpartners.co.uk/iwmp/
 
Description Engineering Matters Podcast 
Form Of Engagement Activity A broadcast e.g. TV/radio/film/podcast (other than news/press)
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Public/other audiences
Results and Impact Interviewed for Engineering Matters podcast on radioactive waste decommissioning and disposal
Year(s) Of Engagement Activity 2020
URL https://engineeringmatters.reby.media/2020/03/13/50-dealing-with-nuclear-waste/
 
Description Expert participant in BEIS public dialogue on Advanced Nuclear Technologies 
Form Of Engagement Activity A formal working group, expert panel or dialogue
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Study participants or study members
Results and Impact I participated as an expert in radioactive waste management for the BEIS-sponsored Public Dialogue on Advanced Nuclear Technology. Groups of the public from different areas of the country discussed the issues around new nuclear power. The outcomes highlighted two key points: (1) the participants of the study were not aware that nuclear power is a modern technology; and (2) they were strongly resolved that there should be no new nuclear power stations until a geological disposal facility for radioactive waste is available. BEIS have taken this on board and are now building in public engagement and waste disposal matters into their emerging Advanced Modular Reactor programme.
Year(s) Of Engagement Activity 2021
URL https://www.gov.uk/government/publications/public-dialogue-on-advanced-nuclear-technologies-ants
 
Description Financial Times interview 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Public/other audiences
Results and Impact Interviewed for Financial Times article "UK returns to grappling with toxic nuclear waste dilemma" - quoted in main article.
Year(s) Of Engagement Activity 2021
URL https://www.ft.com/content/2321bfae-839a-468f-b933-d699b6ff6864
 
Description GDF Conference 2021 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact Prof. Neil Hyatt was invited as the facilitator and panel chair for the Geological Disposal Facility Conference 2021, delivered by Radioactive Waste Management, in recognition of his international standing in the field.
Year(s) Of Engagement Activity 2022
URL https://www.gov.uk/government/news/geological-disposal-programme-now-under-way
 
Description Hunterston B: BBC News 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact Interview on structural integrity of Hunterston B Advanced Gas-cooled Reactor (AGR) by Prof. Neil Hyatt, invited in recognition of expertise in nuclear reactor technology developed through ATLANTIC and PACIFIC consortium research.
Year(s) Of Engagement Activity 2019
URL https://www.bbc.co.uk/news/uk-scotland-47485321
 
Description Hunterston B: Daily Mail 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact Interview on structural integrity of Hunterston B Advanced Gas-cooled Reactor (AGR) by Prof. Neil Hyatt, invited in recognition of expertise in nuclear reactor technology developed through ATLANTIC and PACIFIC consortium research.
Year(s) Of Engagement Activity 2019
URL https://www.dailymail.co.uk/news/article-7117817/Experts-warn-Glasgow-Edinburgh-contaminated-radiati...
 
Description Hunterston B: The Mirror 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact Interview on structural integrity of Hunterston B Advanced Gas-cooled Reactor (AGR) by Prof. Neil Hyatt, invited in recognition of expertise in nuclear reactor technology developed through ATLANTIC and PACIFIC consortium research.
Year(s) Of Engagement Activity 2019
URL https://www.mirror.co.uk/news/uk-news/shocking-footage-reveals-growing-cracks-14105143
 
Description Hunterston B: The Sun 
Form Of Engagement Activity A press release, press conference or response to a media enquiry/interview
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact Interview on structural integrity of Hunterston B Advanced Gas-cooled Reactor (AGR) by Prof. Neil Hyatt, invited in recognition of expertise in nuclear reactor technology developed through ATLANTIC and PACIFIC consortium research.
Year(s) Of Engagement Activity 2019
URL https://www.thesun.co.uk/news/8589454/pics-reveal-cracks-hunterstonb-nuclear-reactors/
 
Description International Festival of Glass 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Public/other audiences
Results and Impact Over 100 visitors met with staff and students at our stall at the International Festival of Glass in Stourbridge, to talk about glass materials and glasses used in radioactive waste management and disposal.
Year(s) Of Engagement Activity 2022
URL https://www.ifg.org.uk/
 
Description Invited Talk at Beihang University summer school at the University of Edinburgh 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Postgraduate students
Results and Impact Invited talk to approximately 50 UG/PG students from Beihang University and University of Edinburgh staff members and PG students as part of their summer school hosted by the University of Edinburgh.
Year(s) Of Engagement Activity 2019
 
Description Invited talk at IEEE University of Edinburgh student chapter 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Postgraduate students
Results and Impact Invited talk at the IEEE student branch of the University of Edinburgh, attended by current and prospective IEEE members.
Year(s) Of Engagement Activity 2020
 
Description Invited talk at the IChemE 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Gave invited talk at IChemE webinar on the application of synchrotron x-ray techniques to understand radioactive materials.
Year(s) Of Engagement Activity 2021
URL https://www.icheme.org/membership/communities/special-interest-groups/nuclear/events/24-02-21-new-op...
 
Description Lead contributor - the Nuclear Dilemma 
Form Of Engagement Activity A broadcast e.g. TV/radio/film/podcast (other than news/press)
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Media (as a channel to the public)
Results and Impact I was filmed for a BBC Ideas short documentary about nuclear power.
Year(s) Of Engagement Activity 2021
URL https://www.bbc.co.uk/ideas/videos/the-nuclear-dilemma/p09rsq3p
 
Description Lucideon visit, Feb 2020 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach Regional
Primary Audience Industry/Business
Results and Impact meeting with Lucideon to discuss routes to fabricate accident tolerant fuels
Year(s) Of Engagement Activity 2020
 
Description Meeting with NNL - July 2019 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach Regional
Primary Audience Industry/Business
Results and Impact Meeting with NNL to discuss progress on National Nuclear Innovation Programme work - direct follow on from PACIFIC and now linked to ATLANTIC
Year(s) Of Engagement Activity 2019
 
Description Monthly Meetings with Westinghouse to discuss Accident Tolerant Fuel research 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact Monthly on-line meetings, convened by Westinghouse USA, to discuss UK-US progress in research in the area of Accident Tolerant Fuels
Year(s) Of Engagement Activity 2022
 
Description NNIP Phase 2 Meeting - Dec 2019 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Policymakers/politicians
Results and Impact Progress meeting, NNIP Phase 2 work. Work linked to TRANSCEND (MOx fuel fabrication) and ATLANTIC (Accident Tolerant Fuel Work). HMG funding Dept BEIS present
Year(s) Of Engagement Activity 2019
 
Description NNIP Phase 2 meeting at Lancaster Nov 2019 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact meeting to discuss progress on National Nuclear Innovation Programme work - linked to TRANSCEND & ATLANTIC
Year(s) Of Engagement Activity 2019
 
Description NNL Accident Tolerant Fuel Visit 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact meeting with NNL to discuss role of ATLANTIC work in National Nuclear Innovation Programme
Year(s) Of Engagement Activity 2019
 
Description National Nuclear Innovation Programme Phase 2 kick off meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact kick off meeting of phase 2 of the national nuclear innovation programme work (sponsored by BEIS) with links to TRANSCEND (MOx fuel fabrication) and ATLANTIC (Accident Tolerant Fuel Work Package)
Year(s) Of Engagement Activity 2019
 
Description Newton Bhabha Fund Researcher Links Workshop "New Electrochemical Technologies for Sustainable Fuels, Chemicals and Industrial Processes" 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Invitation to and participation in Newton Bhabha Fund Researcher Links Workshop "New Electrochemical Technologies for Sustainable Fuels, Chemicals and Industrial Processes", Pune, India, December 2019. This was a workshop for early career researchers from the UK and India working in the area of electrochemistry and electrochemical engineering.
Year(s) Of Engagement Activity 2019
URL http://www.chem.gla.ac.uk/Electrotech2019/
 
Description Participation in NNL's Advanced Nuclear Skills & Innovation Campus Showcase Event 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact The ANSIC showcase highlighted industry and academia collaborations through a range of engaging presentations, celebrating projects that have helped accelerate the deployment of advanced nuclear technologies.
Lancaster researchers presented a poster: "Advanced Technology Fuels in support of Net Zero And DeCarbonisation". The topic of the poster featured in the day's plenary presenation.
Year(s) Of Engagement Activity 2022
URL https://www.niauk.org/advanced-nuclear-skills-and-innovation-campus-showcase-30-03-22/
 
Description Pitch talk to AFCP quarterly meeting 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact A quarterly technical meeting of the entire Advanced Fuel Cycle Programme (AFCP) led by National Nuclear Laboratory delivered primarily for the Department of BEIS as the customers of the AFCP. A short talk was delivered focussing on the technical capabilities that have been developed within this project - specifically density, viscosity and interfacial tension measurements for solvent systems that can include radioactive materials. Interest was received from other attendees to collaborate and perform such measurements to support other projects in aqueous recycle of spent nuclear fuel.
Year(s) Of Engagement Activity 2020
 
Description Presentation at TRANSCEND 1st Annual Meeting (Bath) 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Overview presentation on the ATLANTIC consortium.
Year(s) Of Engagement Activity 2019
 
Description Presentation at annual workshop organised by EC funded project GENIORS 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Participation and presentation at annual workshop oranised by the H2020 funded GENIORS program
Year(s) Of Engagement Activity 2019,2020
 
Description Presentation to Allerdale Borough Council on behalf of CoRWM 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach Local
Primary Audience Other audiences
Results and Impact Delivered presentation to Allerdale Borough Council (part of the Allerdale Geological Disposal Facility Working Group) about CoRWM and support available from CoRWM during the GDF siting process.
Year(s) Of Engagement Activity 2021
 
Description Presentation to EU "Plutonium Management for More Agility" consortium 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact Presentation to EU "Plutonium Management for More Agility" consortium on the reprocessability of accident tolerant fuels
Year(s) Of Engagement Activity 2022
 
Description Presentations at Materials Research Society Meeting in Hawaii, USA 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact Presentations made at Materials Research Society Meeting in Hawaii, USA.
6 oral presentations on: the use of SIMFUELs to predict the behaviour of real fuels; characterisation of SIMFUELs; corrosion studies of real spent nuclear fuel; the role of kinetics in nuclear reprocessing; the role of NO in directing neptunium during advanced nuclear reprocessing schemes; the corrosion behaviour of high-density Advanced Technology Fuels.
2 poster presentations on: advanced oxidation processes for the dissolution of spent nuclear fuel; novel photochemical technologies for the conditions of process streams during advanced reprocessing flowsheets
Year(s) Of Engagement Activity 2022
URL https://www.mrs.org/meetings-events/spring-meetings-exhibits/past-spring-meetings/2022-mrs-spring-me...
 
Description Royal Society Workshop on Nuclear Co-Generation 
Form Of Engagement Activity Participation in an open day or visit at my research institution
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Policymakers/politicians
Results and Impact Prof. Neil Hyatt was invited to participate in the Royal Society meeting on Nuclear Co-generation in recognition of his expertise in radioactive waste management developed through several EPSRC research projects, outcomes from which were highlighted in discussion contribution.
Year(s) Of Engagement Activity 2019
 
Description Spent Fuel Management of High Density Fuels 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Industry/Business
Results and Impact Advanced Fuel Cycle Programme Quaterly Technical Meeting, on-line https://glsr.live/AFCPSept , 22nd - 23rd September 2020
Year(s) Of Engagement Activity 2020
 
Description Talk given to Advanced Fuel Cycle Programme Technical Meeting - Aqueous Recycle 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact A technical meeting of Advanced Fuel Cycle Programme (AFCP) - Aqueous Recycle led by National Nuclear Laboratory focussing primarily on the technical outputs of the AFCP aqueous recycle work and associated project . A 20 minute talk was delivered focussing on the technical outputs that have been developed within this project with data on density, viscosity and interfacial tension across numerous for solvent systems including those loaded with uranium. Interest was received from other attendees to collaborate and perform such measurements to support other projects in aqueous recycle of spent nuclear fuel.
Year(s) Of Engagement Activity 2021
 
Description The nuclear dilemma 
Form Of Engagement Activity A broadcast e.g. TV/radio/film/podcast (other than news/press)
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Public/other audiences
Results and Impact Prof Claire Corkhill was featured in the BBC short "The nuclear dilemma", explaining the nature, management and disposal of radioactive wastes in the context of nuclear power generation to address climate change and the Fukushima dai-ici accident.
Year(s) Of Engagement Activity 2021
URL https://www.bbc.co.uk/ideas/videos/the-nuclear-dilemma/p09rsq3p
 
Description update to Nuclear Academic Discussion Meetings 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Other audiences
Results and Impact update to annual NADM on Atlantic
Year(s) Of Engagement Activity 2020