UTGARD LAB PHASE II: A SIMFUEL FABRICATION & CHARACTERISATION FACILITY
Lead Research Organisation:
Lancaster University
Abstract
The UK currently derives ~16% of its electricity from nuclear fission which constitutes a significant proportion of our low-carbon power. For this to continue, and for our energy use to be decarbonised as is planned, new nuclear plant will be needed well into the future. The UK's history as a nuclear fission pioneer has left a legacy of spent nuclear fuel (SNF) in storage that is projected to grow to 6200 teU of UO2-based fuel over the lifetime of the national Advanced Gas cooled Reactor (AGR) fleet and the Light Water Reactor (LWR) at Sizewell. If new build is implemented to current projected capacity, this will lead to a further ~16,000 teU of UO2-based spent LWR fuel.
Depending on the policies of individual nuclear nations, SNF is either reprocessed or destined to be disposed of in Geologic Disposal Facilities (GDFs). Development of advanced, safer reprocessing cycles or safe wet/dry storage, retrieval and subsequent consignment to GDF requires a detailed understanding of the evolution and behaviour of SNF under conditions relevant to those activities. In the UK, the very high radiation fields arising from real SNF prohibits their study in all but a few specialised "hot cells" operated by Sellafield or NNL. This access is necessarily resource constrained, so impeding the advancing of knowledge in key areas of SNF research.
One way to obviate this problem is to work on simulated SNF (SIMFUELs) consisting of e.g. specially prepared UO2 (depleted) pellets with the same microstructures expected for real SNF with chemical components added to simulate plutonium and fission products formed in-reactor. Ready availability of a wide range of SIMFUEL compositions would both accelerate and enhance understanding of the relative roles of different phases in SNF and mechanistic understanding of key fuel behaviours.
Currently, SIMFUEL fabrication in the UK is only conducted at NNL, which again presents access issues. Thus, the vision for this proposal is to establish a university facility for SIMFUEL fabrication & characterisation - a facility that will be unique within the UK HEI landscape and, by offering open access to external users, will serve to drive and accelerate UK SNF research.
Reflecting the fuel used in the UK's current AGRs & LWR, and to be used in new build LWRs, our focus will be on oxide SIMFUELs - although, with an eye to future fuel cycles, this will include MOX and ThO2-based fuels. The proposed facility will therefore initiate, support and enable research in the following themes:
Theme 1: The development of new, advanced sintering routes for the fabrication of SIMFUELs with porosities, fission product loadings, and defect microstructures that better simulate those of real SNF.
Theme 2: Study of the behaviour of these advanced SIMFUELs, as well as those prepared using conventional ceramic processing techniques, under a range of conditions relevant to the back end of the fuel cycle - including wet/dry interim storage, geologic disposal and new reprocessing routes.
Potential academic users include any concerned with the fundamental physical, chemical and materials properties of SNF, its storage, recycle and disposal. This includes not only the decommissioning / disposal focussed EPSRC TRANSCEND Consortium and the BEIS-funded National Nuclear Innovation Programme in Recycle and Waste management, but also those nuclear CDT students working in this area. Industrially, we have already sequestered interest from RWM Ltd, NNL and Sellafield who would wish to commission the fabrication of samples on a more flexible basis than currently available. To have such a national facility will be a great enabler not only for UK users but also for fission research collaborators from overseas as some international laboratories report great difficulty in getting access to SIMFUEL samples that can be produced & delivered quickly and in a range of compositions iteratively informed by on-going research programmes.
Depending on the policies of individual nuclear nations, SNF is either reprocessed or destined to be disposed of in Geologic Disposal Facilities (GDFs). Development of advanced, safer reprocessing cycles or safe wet/dry storage, retrieval and subsequent consignment to GDF requires a detailed understanding of the evolution and behaviour of SNF under conditions relevant to those activities. In the UK, the very high radiation fields arising from real SNF prohibits their study in all but a few specialised "hot cells" operated by Sellafield or NNL. This access is necessarily resource constrained, so impeding the advancing of knowledge in key areas of SNF research.
One way to obviate this problem is to work on simulated SNF (SIMFUELs) consisting of e.g. specially prepared UO2 (depleted) pellets with the same microstructures expected for real SNF with chemical components added to simulate plutonium and fission products formed in-reactor. Ready availability of a wide range of SIMFUEL compositions would both accelerate and enhance understanding of the relative roles of different phases in SNF and mechanistic understanding of key fuel behaviours.
Currently, SIMFUEL fabrication in the UK is only conducted at NNL, which again presents access issues. Thus, the vision for this proposal is to establish a university facility for SIMFUEL fabrication & characterisation - a facility that will be unique within the UK HEI landscape and, by offering open access to external users, will serve to drive and accelerate UK SNF research.
Reflecting the fuel used in the UK's current AGRs & LWR, and to be used in new build LWRs, our focus will be on oxide SIMFUELs - although, with an eye to future fuel cycles, this will include MOX and ThO2-based fuels. The proposed facility will therefore initiate, support and enable research in the following themes:
Theme 1: The development of new, advanced sintering routes for the fabrication of SIMFUELs with porosities, fission product loadings, and defect microstructures that better simulate those of real SNF.
Theme 2: Study of the behaviour of these advanced SIMFUELs, as well as those prepared using conventional ceramic processing techniques, under a range of conditions relevant to the back end of the fuel cycle - including wet/dry interim storage, geologic disposal and new reprocessing routes.
Potential academic users include any concerned with the fundamental physical, chemical and materials properties of SNF, its storage, recycle and disposal. This includes not only the decommissioning / disposal focussed EPSRC TRANSCEND Consortium and the BEIS-funded National Nuclear Innovation Programme in Recycle and Waste management, but also those nuclear CDT students working in this area. Industrially, we have already sequestered interest from RWM Ltd, NNL and Sellafield who would wish to commission the fabrication of samples on a more flexible basis than currently available. To have such a national facility will be a great enabler not only for UK users but also for fission research collaborators from overseas as some international laboratories report great difficulty in getting access to SIMFUEL samples that can be produced & delivered quickly and in a range of compositions iteratively informed by on-going research programmes.
Planned Impact
Aside from academic beneficiaries identified elsewhere on this form, beneficiaries of the R&D that will be underpinned and accelerated by the proposed UTGARD SIMFUEL Facility fall into three distinct groups:
1. The nuclear industry, including but not limited to nuclear site licence companies (e.g. Sellafield Ltd, EdF, Westinghouse Springfields Fuel Ltd) and their supply chains,
2. Government & associated bodies (e.g. the Department of Business, Energy & Industrial Strategy), policy makers (e.g. the Nuclear Innovation & Research Advisory Board), regulators and implementation authorities (e.g. the Nuclear Decommissioning Authority, National Nuclear Laboratory, Radioactive Waste Management Ltd), and
3. Society and the general public.
We envisage that the R&D and associated activities facilitated will have significant impact in four key domains of relevance to our end-users and stakeholders:
1. Knowledge, by fostering the creation of new fundamental understanding and technologies to help address challenges in the management of spent nuclear fuel (SNF), hence leading to long term economic, social, environmental, safety, health and security benefits associated with improved SNF storage, disposal and recycling.
2. People, through training and supporting the development of the scientists and engineers who access the facility, providing them with the skills, experience and knowledge of direct relevance to the nuclear sector, so supporting the Nuclear Skills Pipeline;
3. Economy, through accelerating the generation of exploitable research results supporting reductions in the costs of SNF storage & geological disposal and the development of new fuel recycling processes that may reduce future environmental & financial burdens, leading in turn to the creation of indigenous IP strengthening of the competitiveness of the UK civil nuclear sector, and ultimately to job creation though technology commercialisation; and
4. Society, by informing UK energy, environmental & industrial policies, regulatory regimes and by supporting a reduction in the hazard, timescales and cost to the taxpayer associated with SNF storage, disposal and/or recycle - the latter enhancing public acceptance of nuclear power and, especially, geological disposal immediately prior to the launch of the Geologic Disposal Facility siting process.
1. The nuclear industry, including but not limited to nuclear site licence companies (e.g. Sellafield Ltd, EdF, Westinghouse Springfields Fuel Ltd) and their supply chains,
2. Government & associated bodies (e.g. the Department of Business, Energy & Industrial Strategy), policy makers (e.g. the Nuclear Innovation & Research Advisory Board), regulators and implementation authorities (e.g. the Nuclear Decommissioning Authority, National Nuclear Laboratory, Radioactive Waste Management Ltd), and
3. Society and the general public.
We envisage that the R&D and associated activities facilitated will have significant impact in four key domains of relevance to our end-users and stakeholders:
1. Knowledge, by fostering the creation of new fundamental understanding and technologies to help address challenges in the management of spent nuclear fuel (SNF), hence leading to long term economic, social, environmental, safety, health and security benefits associated with improved SNF storage, disposal and recycling.
2. People, through training and supporting the development of the scientists and engineers who access the facility, providing them with the skills, experience and knowledge of direct relevance to the nuclear sector, so supporting the Nuclear Skills Pipeline;
3. Economy, through accelerating the generation of exploitable research results supporting reductions in the costs of SNF storage & geological disposal and the development of new fuel recycling processes that may reduce future environmental & financial burdens, leading in turn to the creation of indigenous IP strengthening of the competitiveness of the UK civil nuclear sector, and ultimately to job creation though technology commercialisation; and
4. Society, by informing UK energy, environmental & industrial policies, regulatory regimes and by supporting a reduction in the hazard, timescales and cost to the taxpayer associated with SNF storage, disposal and/or recycle - the latter enhancing public acceptance of nuclear power and, especially, geological disposal immediately prior to the launch of the Geologic Disposal Facility siting process.
Publications

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

Anderson C
(2022)
The TRANSCEND University Consortium Theme 4: Nuclear materials






Description | The UK currently derives ~16% of its electricity from nuclear fission which constitutes a significant proportion of our low-carbon power. For this to continue, and for our energy use to be decarbonised as is planned, new nuclear plant will be needed well into the future. The UK's history as a nuclear fission pioneer has left a legacy of spent nuclear fuel (SNF) in storage that is projected to grow to 6200 teU of UO2-based fuel over the lifetime of the national Advanced Gas cooled Reactor (AGR) fleet and the Light Water Reactor (LWR) at Sizewell. If new build is implemented to current projected capacity, this will lead to a further ~16,000 teU of UO2-based spent LWR fuel. Depending on the policies of individual nuclear nations, SNF is either reprocessed or destined to be disposed of in Geologic Disposal Facilities (GDFs). Development of advanced, safer reprocessing cycles or safe wet/dry storage, retrieval and subsequent consignment to GDF requires a detailed understanding of the evolution and behaviour of SNF under conditions relevant to those activities. In the UK, the very high radiation fields arising from real SNF prohibits their study in all but a few specialised "hot cells" operated by Sellafield or NNL. This access is necessarily resource constrained, so impeding the advancing of knowledge in key areas of SNF research. One way to obviate this problem is to work on simulated SNF (SIMFUELs) consisting of e.g. specially prepared UO2 (depleted) pellets with the same microstructures expected for real SNF with chemical components added to simulate plutonium and fission products formed in-reactor. Ready availability of a wide range of SIMFUEL compositions would both accelerate and enhance understanding of the relative roles of different phases in SNF and mechanistic understanding of key fuel behaviours. Currently, SIMFUEL fabrication in the UK is only conducted at NNL, which again presents access issues. Thus, the vision for this proposal is to establish a university facility for SIMFUEL fabrication & characterisation - a facility that will be unique within the UK HEI landscape and, by offering open access to external users, will serve to drive and accelerate UK SNF research. Reflecting the fuel used in the UK's current AGRs & LWR, and to be used in new build LWRs, our focus will be on oxide SIMFUELs - although, with an eye to future fuel cycles, this will include MOX and ThO2-based fuels. The proposed facility will therefore initiate, support and enable research in the following themes: Theme 1: The development of new, advanced sintering routes for the fabrication of SIMFUELs with porosities, fission product loadings, and defect microstructures that better simulate those of real SNF. Theme 2: Study of the behaviour of these advanced SIMFUELs, as well as those prepared using conventional ceramic processing techniques, under a range of conditions relevant to the back end of the fuel cycle - including wet/dry interim storage, geologic disposal and new reprocessing routes. Potential academic users include any concerned with the fundamental physical, chemical and materials properties of SNF, its storage, recycle and disposal. This includes not only the decommissioning / disposal focussed EPSRC TRANSCEND Consortium and the BEIS-funded National Nuclear Innovation Programme in Recycle and Waste management, but also those nuclear CDT students working in this area. Industrially, we have already sequestered interest from RWM Ltd, NNL and Sellafield who would wish to commission the fabrication of samples on a more flexible basis than currently available. To have such a national facility will be a great enabler not only for UK users but also for fission research collaborators from overseas as some international laboratories, report great difficulty in getting access to SIMFUEL samples that can be produced & delivered quickly and in a range of compositions iteratively informed by on-going research programmes. |
Exploitation Route | The vision and aim for this proposal is to establish a university facility for simulated spent nuclear fuel (SIMFUEL) fabrication & characterisation, for that facility to be unique within the UK HEI landscape and, by offering open access to external users, for that facility to drive and accelerate UK research into the storage, recycle and disposal of spent nuclear fuel. The specific objectives supporting the realisation of this vision / aim are as follows: 1. To deliver a cutting-edge, world-leading nuclear research facility by the end of FY 2020/2021 by: (i) extension of Lancaster's existing radiochemical lab for open sources, UTGARD Lab (Uranium/Thorium beta-Gamma Active R&D Lab); and (ii) the siting of a bundle of closely aligned equipment therein to create an effective single SIMFUEL R&D facility. 2. By siting of the proposed facility within UTGARD Lab, to leverage significant co-located supporting equipment and attract minimal infrastructural and administrative overheads. 3. By siting the proposed facility within UTGARD Lab, to exploit its existing user base and to improve further on its NUFF-audited 33% usage by external users. 4. To focus on oxide fuels so as (i) to reflect the fuel used in the UK's current AGRs & LWR, and to be used in new build LWRs, to focus on oxide SIMFUELs; and (ii) to future protect the facility by including oxide fuels for future fuel cycles such as MOX (both existing heterogeneous MOX and new homogeneous formulations) and ThO2-based fuels. 5. Facilitated by the co-location with UTGARD Lab and the focus on oxide fuels, to expand NNUF Phase 1 facilities to include a distinct cradle-to-grave facility, that allows for wet precursor to dry SIMFUEL fabrication & characterisation to take place under one roof and that supports and complements the BEIS Nuclear Innovation Programme 6. To develop new, advanced sintering routes for the fabrication of SIMFUELs with porosities, fission product loadings, and defect microstructures that better simulate those of real SNF 7. Using these advanced SIMFUELs, as well as those prepared using conventional ceramic processing techniques to develop, from FY 2020/2021 onwards, innovative technical capabilities and solutions in key strategic areas identified by NIRAB - specifically wet/dry interim storage, geologic disposal and new reprocessing routes. 8. To enhance the position and reputation of the UK in nuclear research over the coming decade by increasing the output of high-impact research in the area of spent nuclear fuel by avoiding access and operator exposure issues associated with working with real spent nuclear fuel. 9. To enable the development of affordable, cost-effective solutions for national research by 2025 in support of the new-build & future decommissioning programmes by avoiding cost and security issues associated with working with real spent nuclear fuel. 10. To enable national & international research collaborations from financial year 2020/2021 between academia & industry by minimising cost and the materials transfer permissioning issues associated with SIMFUELs fabricated on nuclear licensed sites. 11. To create a library of well characterised SIMFUELs for use by those researchers that do not wish to create their own materials by retaining samples of each simulant created by UTGARD researchers, with permission, those created by external users |
Sectors | Energy |
URL | https://www.nnuf.ac.uk/utgard-laboratory |
Description | UTGARD was used extensively by Lancaster Researchers to conduct research for the UK's BEIS-funded Advanced Fuel Cycle Programme. Research occurred and is still ongoing in two areas: 1. Advanced reprocessing routes for the recycling of spent nuclear fuel; and 2. The development of routes to accident tolerant fuels and the understanding of their behaviour during post irradiation storage, disposal and reprocessing Work in the first area has led to a collaboration with the European Space Agency in the area of americium-bearing fuels for satellite applications. Work in the second area has led to a number of further wards: - one in the area of accident tolerant fuels for advanced nuclear reactor designs (funded through the BEIS Advanced Nuclear Science & Innovation Campus pilot scheme) - three in the area of coated particle fuels, again for advanced nuclear reactor designs, resulting in the first fabrication of TRISO (TRi-structural ISOtropic particle fuel) kernels in a university laboratory since the mid-1970s. - one in the area of radioisotope thermoelectric generators (RTG) for space craft, funded by the European Space Agency Post-relaxation of COVID restrictions, UTGARD is now open to other external users including: University of Leeds - who are fabricating silicide fuel surrogates in UTGARD University of Sheffield - who are fabricating uranium and thorium holding zirconolite wasteforms in UTGARD University of Liverpool - who are synthesising mixed U/Ce oxides for disposal MOX applications in UTGARD University of Leicester - who are producing RTG pellet precursors in UTGARD Rolls Royce Derby - who have conducted inspections of novel zircalloy formulations for cladding of advanced nuclear fuels for small modular reactors LiNa Energy - who have used UTGARDs facilities for the characterisation of novel battery components |
Sector | Chemicals,Education,Energy,Environment |
Impact Types | Societal |
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 | £2,545,629 (GBP) |
Funding ID | EP/S011935/1 |
Organisation | Engineering and Physical Sciences Research Council (EPSRC) |
Sector | Public |
Country | United Kingdom |
Start | 12/2018 |
End | 11/2022 |
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 |
Amount | £120,000 (GBP) |
Funding ID | National Nuclear Laboratory Agreement No NNL/UA/137 |
Organisation | National Nuclear Laboratory |
Sector | Public |
Country | United Kingdom |
Start | 09/2021 |
End | 09/2025 |
Description | MOX SIMFUELs - Development of Simulants |
Amount | £100,000 (GBP) |
Organisation | Nuclear Decommissioning Authority NDA |
Department | Radioactive Waste Management |
Sector | Public |
Country | United Kingdom |
Start | 12/2019 |
End | 11/2023 |
Description | NNL Advanced Fuel Cycle Programme NNL/NIP/0066 - UO2 Kernels for Coated Particle Fuels |
Amount | £75,000 (GBP) |
Funding ID | NNL/NIP/0066 |
Organisation | National Nuclear Laboratory |
Sector | Public |
Country | United Kingdom |
Start | 11/2021 |
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 | 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 | SICODELIQ - SImulated COntamination assisted DEcontamination of highly active LIQuid facilities |
Amount | £29,200 (GBP) |
Funding ID | National Nuclear Laboratory Agreement No NNL/UA/ |
Organisation | National Nuclear Laboratory |
Sector | Public |
Country | United Kingdom |
Start | 09/2021 |
End | 09/2025 |
Description | TRANSCEND: Transformative Science and Engineering for Nuclear Decommissioning |
Amount | £4,587,420 (GBP) |
Funding ID | EP/S01019X/1 |
Organisation | Engineering and Physical Sciences Research Council (EPSRC) |
Sector | Public |
Country | United Kingdom |
Start | 08/2018 |
End | 09/2022 |
Description | The Management of Spent Oxide Fuel: Detecting the Onset of Cladding Corrosion Under Irradiated Fuel Storage Pond Conditions |
Amount | £120,000 (GBP) |
Funding ID | NNL/UA/160 |
Organisation | Nuclear Decommissioning Authority NDA |
Sector | Public |
Country | United Kingdom |
Start | 01/2023 |
End | 12/2026 |
Description | The Management of Spent Oxide Fuel: Irradiation of AGR SIMfuels in Pond Storage Environments - Consequences for UO2 Corrosion and Water Radiolysis |
Amount | £60,000 (GBP) |
Organisation | Sellafield Ltd |
Sector | Private |
Country | United Kingdom |
Start | 09/2023 |
End | 09/2027 |
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 | U/Ce Oxides from Oxalate Route |
Amount | £125,000 (GBP) |
Organisation | European Space Agency |
Sector | Public |
Country | France |
Start | 03/2022 |
End | 03/2023 |
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 |
Description | UTGARD Lab Phase II: A SIMFUEL Fabrication & Characterisation Facility |
Amount | £752,056 (GBP) |
Funding ID | EP/T011416/1 |
Organisation | Engineering and Physical Sciences Research Council (EPSRC) |
Sector | Public |
Country | United Kingdom |
Start | 11/2019 |
End | 03/2024 |
Description | Understanding the Volatilisation of Ruthenium |
Amount | £50,000 (GBP) |
Funding ID | Sellafield Ltd Contract No A104820 |
Organisation | Sellafield Ltd |
Sector | Private |
Country | United Kingdom |
Start | 09/2020 |
End | 09/2024 |
Description | Collaboration with Sellafield |
Organisation | Sellafield Ltd |
Country | United Kingdom |
Sector | Private |
PI Contribution | Academic supervision of three research students in the area of spent nuclear fuel and nuclear waste management |
Collaborator Contribution | Industrial supervision and funding of three research students in the area of spent nuclear fuel and nuclear waste management |
Impact | Project early stages at the moment |
Start Year | 2019 |
Description | NNL collaboration in the area of advanced nuclear reprocessing |
Organisation | National Nuclear Laboratory |
Country | United Kingdom |
Sector | Public |
PI Contribution | Working with NNL Subject Matter Experts in the area of advanced nuclear fuel reprocessing through a series of PhD and PDRA positions |
Collaborator Contribution | Supporting Lancaster's work in advanced nuclear fuel reprocessing through a series of PhD and PDRA positions |
Impact | "The hydrolysis of Hydroxamic Acid Complexants in the Presence of Non-Oxidising Metal Ions 1: Ferric Ions", F.P.L.Andrieux, C.Boxall and R.J.Taylor, J.Sol.Chem, 36(10), 1201-1217 (2007). IF = 1.128 "The hydrolysis of Hydroxamic Acid Complexants in the Presence of Non-Oxidising Metal Ions 2: Neptunium (IV) Ions", F.P.L.Andrieux, C.Boxall, I.May and R.J.Taylor, J.Sol.Chem, 37(2), 215-232 (2008). IF = 1.128 "Oxidation-Reduction Reactions of Simple Hydroxamic Acids in the Presence of Plutonium (IV) Ions", M.J.Carrott, O.D.Fox, G.LeGurun, C.J.Jones, C.Mason, R.J.Taylor, F.Andrieux, C.Boxall, Radiochimica Acta, 96(6), 333-344 (2008). IF = 1.373 "Acetohydroxamatoiron (III) complexes: Thermodynamics of formation and temperature dependent speciation", F.P.L.Andrieux, C.Boxall and R.J.Taylor, J.Sol.Chem, 37(11), 1511-1527 (2008). IF = 1.128 "Some aspects of neptunium acetohydroxamic acid chemistry under acid conditions", M.J.Sarsfield, R.J.Taylor, C.Boxall, F.P.L.Andrieux, Radiochimica Acta, 97(4-5), 219-222 (2009). IF = 1.373 "Surface Decontamination by Photocatalysis", R.J.Wilbraham, C.Boxall, R.J.Taylor, Proceedings of ASME 12th International Conference on Environmental Remediation and Radioactive Waste Management,Vol. 2, 185-193 (2010). "A Preliminary Study of the Hydrolysis of Hydroxamic Acid Complexants in the Presence of Oxidising Metal Ions" F.P.L.Andrieux, C.Boxall, I.May, R.J.Taylor IOP Conference Series: Materials Science and Engineering, 9, Article 012081, 8 pages (2010). "Hydrolysis of Hydroxamic Acid Complexants in the Presence of Non-Oxidizing Metal Ions", S.Edwards, F.P.L.Andrieux, C.Boxall, R.J.Taylor, D.Woodhead, in "Materials Challenges in Current and Future Nuclear Technologies", K.R.Whittle, M.Bertolus, B.Uberuaga, R.W.Grimes (Eds), Cambridge University Press, Cambridge UK, Mat. Res. Soc. Symp. Proc., 1383, Article mrsf11-1383-a07-02, 6 pages (2012) DOI: 10.1557/opl.2012.210 "Surface Decontamination by Photocatalysis", R.J.Wilbraham, C.Boxall, R.J.Taylor, S.Woodbury in "Materials Challenges in Current and Future Nuclear Technologies", K.R.Whittle, M.Bertolus, B.Uberuaga, R.W.Grimes (Eds), Cambridge University Press, Cambridge UK, Mat. Res. Soc. Symp. Proc., 1383, Article mrsf11-1383-a07-07, 7 pages (2012) DOI: 10.1557/opl.2012.182 " Photocatalytically Driven Dissolution of Macroscopic Metal Surfaces. Part 1: Silver" R.J.Wilbraham, C.Boxall, R.J.Taylor, J.Photochem.Photobiol A: Chem., 249, 21-28 (2012) DOI: 10.1016/j.jphotochem.2012.09.003 IF = 2.416 "Neptunium (V) oxidation by nitrous acid in nitric acid" C.Gregson, C.Boxall, M.Carrott, S.Edwards, M.Sarsfield, R.Taylor, D.Woodhead, in "Atalante 2012 International Conference on Nuclear Chemistry for Sustainable Fuel Cycles", C.Poinsott (Ed), Elsevier, London UK, Procedia Chemistry, 7, 398-403 (2012). DOI: 10.1016/j.proche.2012.10.062 IF = 0.4 "The hydrolysis of Hydroxamic Acid Complexants in the Presence of Non-Oxidising Metal Ions 3: Ferric Ions at elevated temperatures", F.P.L.Andrieux, C.Boxall, H.Steele and R.J.Taylor, J.Sol.Chem, 43(3) 608-622 (2014). DOI 10.1007/s10953-014-0142-y IF = 1.128 "The Effect of Hydrogen Peroxide on the Dissolution of Electrodeposited Uranium Oxide Films on 316L Stainless Steel" " R.J.Wilbraham, C.Boxall, R.J.Taylor, S.Woodbury, J.Nuc.Mat., 464, 86-96 (2015). DOI 10.1016/j.jnucmat.2015.04.007 IF = 2.09 "A Study of Cerium Extraction by TBP and TODGA using a Rotating Diffusion Cell" M.A.Bromley, C.Boxall, Nukleonika, 60(4), 859-864 (2015). DOI: 10.1515/nuka-2015-0121 IF=0.477 "Simulation of Neptunium extraction in an Advanced PUREX process - model improvement", H.Chen, R.J.Taylor, M.Jobson, D.A.Woodhead, C.Boxall, A.J.Masters, S.Edwards, Solvent Extraction & Ion Exchange, 35(1), 1-18 (2017). DOI: 10.1080/07366299.2016.1273684 IF = 2.05 "The Effects of Nitric Acid on Extraction Properties of TODGA During Fission Product Management", M.A.Bromley, C.Boxall in "The Scientific Basis of Nuclear Waste Management", N.C.Hyatt, R.Ewing, Y.Inagaki, C.Jantzen (Eds), Cambridge University Press, Cambridge UK, MRS Advances., 2(10), 563-568 (2017) DOI: 10.1557/adv.2016.624 "Photocatalytically driven dissolution of macroscopic nickel surfaces", R.J.Wilbraham, C.Boxall, R.J.Taylor, Corrosion Science, 131, 137-146 (2017). DOI: 10.1016/j.corsci.2017.11.018 IF = 5.3 "Neptunium(IV)-hydroxamate complexes: their speciation, and kinetics and mechanism of hydrolysis", S.Edwards, F.Andrieux, C.Boxall, M.Sarsfield, R. Taylor and D.Woodhead, Dalton Trans., 48, 673 - 687 (2019). DOI: 10.1039/c8dt02194e IF = 4.099. "Nitrous acid-driven reduction of vanadium as a neptunium analogue ", M.Chimes, C.Boxall, S.Edwards, M.Sarsfield, R.J.Taylor D.Woodhead, Prog.Nucl.Sci.Tech, 5, 37-40 (2018). DOI: 10.15669/pnst.5.37 "A Study of Cerium Extraction Kinetics by TODGA in Acidified and Non-Acidified Organic Solvent Phases in the Context of Fission Product Management", M.A.Bromley, C.Boxall, Prog.Nucl.Sci.Tech, 5, 70-73 (2018). DOI: 10.15669/pnst.5.70 |
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 | 25 fortnightly meetings with NNL to review progress in decontamination research projects |
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 | 25 fortnightly meetings with NNL to discuss progress in decontamination research. associated students are funded by NNL/Sellafield's Centre for Innovative Nuclear Decommissioning (CINDe) and are affiliated to the TRANSCEND consortium. |
Year(s) Of Engagement Activity | 2020,2021 |
Description | AFCP Progress Review 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 | Meeting to review progress of university partners in the reprocessing work packages of the UK's Advanced Fuel Cycle Programme |
Year(s) Of Engagement Activity | 2021 |
Description | AFCP Progress Review 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 | July 2020 meeting with NNL to review Lancaster's progress on reprocessing work packages of UK's Advanced Fuel Cycle Programme |
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 | Aqueous Recycle Project, Theme 1: Flowsheet development: Work Package 3: Finishing |
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 | Presentation and discussion of progress made in Lancaster's work on the UK's Advanced Fuel Cycle Programme |
Year(s) Of Engagement Activity | 2020 |
Description | Attendance at Radioactive Waste Management Spent Fuel Strategy Workshop |
Form Of Engagement Activity | A formal working group, expert panel or dialogue |
Part Of Official Scheme? | No |
Geographic Reach | International |
Primary Audience | Industry/Business |
Results and Impact | Attendance at Radioactive Waste Management Spent Fuel Strategy Workshop, online, 8th October 2021. Purpose to develop RWM's research strategy in this area. Made invited presentation as follows: "Update on AGR SIMFUEL Studies at Lancaster", C.Boxall, N.Rauff-Nisthar, E.Howett, R.Wilbraham, G.Berhane, S.Jones, I.Robertson |
Year(s) Of Engagement Activity | 2021 |
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 | Integrated Finishing Studies |
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 | Invited Presentation "The Nuclear Option(s)" |
Form Of Engagement Activity | A talk or presentation |
Part Of Official Scheme? | No |
Geographic Reach | International |
Primary Audience | Industry/Business |
Results and Impact | Invited Presentation "The Nuclear Option(s)", C. Boxall, Engineering the Energy Tranistion Conference, The Bryden Centre, The Titanic Hotel, Belfast, 27th - 28th February 2020 |
Year(s) Of Engagement Activity | 2020 |
Description | Meeting to promote UK Active Facilities |
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 | Feb 2020 Meeting at Sheffield to promote UK National Nuclear User Facilities to potential users. |
Year(s) Of Engagement Activity | 2020 |
Description | Meeting to promote UK NNUF Facilities |
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 | June 2020 meeting to promote UK National Nuclear User Facilities to potential users |
Year(s) Of Engagement Activity | 2020 |
Description | Meeting with NNL to discuss use of UTGARD |
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 | Industry/Business |
Results and Impact | 14th Oct 2020 meeting with NNL to discuss their possible use of UTGARD Lab |
Year(s) Of Engagement Activity | 2020 |
Description | Meeting with NNL to review progress on UK's Advanced Fuel Cycle Programme |
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 | Nov 2020 meeting with NNL to review Lancaster's progress on reprocessing work packages of UK's Advanced Fuel Cycle Programm |
Year(s) Of Engagement Activity | 2020 |
Description | Meeting with Radioactive Waste Management Ltd |
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 radioactive waste management ltd to discuss progress on mixed oxide nuclear fuel project |
Year(s) Of Engagement Activity | 2020 |
Description | Meeting with the European Space Agency |
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 | Meeting with European Space Agency to present progress on project to develop Radioisotope Thermoelectric Generators to power spacecraft. |
Year(s) Of Engagement Activity | 2022 |
Description | Participation in NNL's Advanced Fuel Cycle Programme 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 | UK's national nuclear lab hosts BEIS, world-leading academia and industry at pioneering showcase events The National Nuclear Laboratory (NNL) hosted world-leading researchers, business, supply chain and government officials to celebrate the success of two headline projects, highlighting the role that nuclear plays in reaching net zero by 2050. Held on the 30 & 31 March at the Preston Marriott Hotel, each day was designated to celebrating one of NNL's key projects, delivered in partnership with BEIS - the Advanced Nuclear Skills and Innovation Campus (ANSIC) pilot and the Advanced Fuel Cycle Programme (AFCP). In total, 430 delegates were in attendance. Lancaster researchers presented posters on their work on advanced reprocessing routes for spent fuel and on the fabrication of the UO2 kernels for Coated Particle Fuels, the fuel of choice for the UK's proposed Advanced Modular Reactor |
Year(s) Of Engagement Activity | 2022 |
URL | https://www.nnl.co.uk/2022/04/uks-national-nuclear-lab-hosts-beis-and-world-leading-academia-and-ind... |
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 | Presentation at TRANSCEND Annual Conference |
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 | 1 oral presentation at the TRANSCEND Annual Meeting as follows "Safe Interim Storage of plutonium: Electrochemical investigations on doped plutonium oxide", D.Laventine, C.Boxall, D.Wegen, TRANSCEND 2nd Annual Meeting, DoubleTree by Hilton Harrogate Majestic Hotel, 10th - 12th November 2021, 3 poster presentations at the TRANSCEND Annual Meeting as follows: "The Radiolysis of Water over Plutonium Dioxide: A Study of H2/O2 Recombination Processes", C.Williams, C.Boxall, H.Steele, R.Orr "MOX SIMfuels: Production and Preliminary Studies of Homogeneous U:CeO2 SIMfuels", I.Robertson, C.Boxall, D.Hambley, R.Hibberd, R.Wilbraham "Interaction of Water with PuO2 Analogues", D.Laventine, C.Boxall, R.Taylor, R.Orr |
Year(s) Of Engagement Activity | 2021 |
URL | https://transcendconsortium.org/document-library/ |
Description | Presentation at the 99. Radioactive Waste Management Research Support Office Annual Conference |
Form Of Engagement Activity | A talk or presentation |
Part Of Official Scheme? | No |
Geographic Reach | National |
Primary Audience | Industry/Business |
Results and Impact | Poster presentation at the RWM RSO Annual conference as follows: Radioactive Waste Management Research Support Office Annual Conference, Hyatt Regency Manchester, 15th - 16th September 2021, "UTGARD Lab - A SIMFUEL Fabrication Facility", R.Wilbraham, C.Boxall |
Year(s) Of Engagement Activity | 2021 |
URL | https://www.research-support-office-gdf.ac.uk/connect/previous-events/ |
Description | Presentation at the Nuclear Waste Services Research Support Office Annual Conference, Jan 2023 |
Form Of Engagement Activity | Participation in an activity, workshop or similar |
Part Of Official Scheme? | No |
Geographic Reach | International |
Primary Audience | Policymakers/politicians |
Results and Impact | Poster presentations at NWS Annual Conference on UTGARD and Development of MOX SIMFUELs |
Year(s) Of Engagement Activity | 2022 |
Description | Presentation on UTGARD to NNUF Symposium, Oxford, Dec 2022 |
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 | Presentation on UTGARD to NNUF Symposium, Oxford, Dec 2022 |
Year(s) Of Engagement Activity | 2022 |
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 | Presentation to European Spent Fuel Workshop 22 in Barcelona |
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 | Review presentation on Lancaster's SIMFUEL research to the Spent Fuel Workshop 22 conference in Barcelona |
Year(s) Of Engagement Activity | 2022 |
URL | https://sfw22.amphos21.com/ |
Description | Presentation to NNL Off Gas 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 | presentation to oak ridge national lab and NNL on recent work in embedding volatile fission products into SIMFUELs |
Year(s) Of Engagement Activity | 2022 |
Description | Presentation to The National Nuclear Users Facility Annual Symposium |
Form Of Engagement Activity | Participation in an activity, workshop or similar |
Part Of Official Scheme? | No |
Geographic Reach | National |
Primary Audience | Study participants or study members |
Results and Impact | Presentation at the NNUF Symposium 2022 as follows: "UTGARD Lab - A SIMFUEL Fabrication Facility", R.Wilbraham, C.Boxall, The National Nuclear Users Facility Annual Symposium, online, 13th January 2022 |
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 | Presentations at TRANSCEND Theme Meeting (May 2022) and Annual Conference (Nov 2022) |
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 at TRANSCEND Theme Meeting (May 2022) and Oral Presentation on the development of MOX SIMFUELs Oral Presentation on the corrosion behaviour of real spent nuclear fuel Oral presentation on the the possible oxidation of PuO2 to PuO2+x Oral Presentation at the TRANSCEND Annual Conference (Nov 2022) on the characterisation of SIMFUELs Poster presentation on the development of MOX SIMFUELs |
Year(s) Of Engagement Activity | 2022 |
URL | https://transcendconsortium.org/events/ |
Description | Presentations at Waste Management 2020, USA |
Form Of Engagement Activity | A talk or presentation |
Part Of Official Scheme? | No |
Geographic Reach | International |
Primary Audience | Industry/Business |
Results and Impact | Three presentations at Waste Management 2020 in Phoenix Arizona. Presentations summarising progress on plutonium storage and spent nuclear fuel disposal research within the TRANSCEND consortium |
Year(s) Of Engagement Activity | 2020 |
Description | Presentations at Waste Management 2022, USA |
Form Of Engagement Activity | A talk or presentation |
Part Of Official Scheme? | No |
Geographic Reach | International |
Primary Audience | Industry/Business |
Results and Impact | 4 oral presentations made to WM2022 as follows "Electrokinetic In Situ Decontamination of Entrained Radioactivity Within a Concrete Matrix", T.McCarthy, C.Boxall, M.J.Joyce, A.Banford, Waste Management 2022, Phoenx Convention Centre, Phoenix, Arizona, 6th - 10th March 2022 "Towards the Decontamination of Plutonium Contaminated Bricks: Investigation of Cerium Based Simulant on Brick Penetration", J.Kennedy, C.Boxall, A.Banford, R.Demmer, A.J.Parker, D.Hutchison, Waste Management 2022, Phoenx Convention Centre, Phoenix, Arizona, 6th - 10th March 2022 "Solid-State Electrochemical Oxidation of PuO2 to PuO2+x" D.Laventine, C.Boxall, D.Wegen, Waste Management 2022, Phoenx Convention Centre, Phoenix, Arizona, 6th - 10th March 2022 "The TRANSCEND University Consortium Theme 4: Nuclear material" C. Anderson, L. Blackburn, C. Boxall, C.L. Corkhill, M. Dixon Wilkins, F. Currell, X. Han, J.W. Hobbs, N.C. Hyatt, N. Kaltsoyannis, M. Kuman, D. Laventine, S. Murphy, E. Murray, W. Neilson, R. Orr, M. Read, H. Steele, S.-K. Sun, Waste Management 2022, Phoenx Convention Centre, Phoenix, Arizona, 6th - 10th March 2022 Plus two poster presentations "The Radiolysis of Water over Plutonium Dioxide: A Study of H2/O2 Recombination Processes", C.Williams, C.Boxall, H.Steele, R.Orr "Electrokinetic In Situ Decontamination of Entrained Radioactivity Within a Concrete Matrix", T.McCarthy, C.Boxall, M.J.Joyce, A.Banford |
Year(s) Of Engagement Activity | 2022 |
URL | http://wmsym.org |
Description | Presentations to Technical Meetings of the UK Advanced Fuel Cycle Programme |
Form Of Engagement Activity | A talk or presentation |
Part Of Official Scheme? | No |
Geographic Reach | International |
Primary Audience | Industry/Business |
Results and Impact | 5 presentations as follows: "Advanced Aqueous Recycle: Fuel Dissolution and Finishing", C.Boxall, M.Bromley, S.Jones, M.Chimes, R.Wilbraham, Advanced Fuel Cycle Programme Quaterly Technical Meeting, online https://glsr.live/AFCPApr, 27th - 28th April 2021. "Integrated Finishing Studies - Aqueous Recycle" C.Boxall, M.Bromley, S.Jones, M.Chimes, R.Wilbraham, Advanced Fuel Cycle Programme Technical Close Out Meeting, online https://glsr.live/AFCPOct, 14th Oct 2021. "Advanced Aqueous Recycle (Theme 1): Fuel Dissolution and Finishing (WP1 & WP3)", C.Boxall, M.Bromley, S.Jones, M.Chimes, R.Wilbraham, Advanced Fuel Cycle Programme Recycle Technical Close Out Meeting, University of Manchester, 3rd November 2021. "Progress on an innovative photo-reactor for U,Pu coprocessing", M.Bromley, C.Boxall, Advanced Fuel Cycle Programme Technical Close Out Meeting, University of Manchester, 3rd November 2021. "Progress in Work Package 1 - Dissolution", M.Chimes, C.Boxall, Advanced Fuel Cycle Programme Technical Close Out Meeting, University of Manchester, 3rd November 2021. |
Year(s) Of Engagement Activity | 2021 |
URL | https://afcp.nnl.co.uk/ |
Description | Progress Review Meeting with NNL |
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 | May 2020 meeting with NNL to review progress in TRANSCEND and Advanced Fuel Cycle Programme Research Projects |
Year(s) Of Engagement Activity | 2020 |
Description | Progress on an innovative photo-reactor for U,Pu coprocessing |
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, online https://glsr.live/AFCPDec , 16th - 17th December 2020 |
Year(s) Of Engagement Activity | 2020 |
Description | Radioactive Waste Management Ltd 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 | Meeting with Radioactive Waste Management to discuss future project on understanding the behaviour of spent nuclear fuel under disposal conditions. |
Year(s) Of Engagement Activity | 2021 |
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 | TRANSCEND Theme Meetings - On-line Dec 2020 |
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 | TRANSCEND Theme Meetings - 1. Theme 3 - Spent Nuclear Fuel 2. Theme 4 - Nuclear Materials Held on-line Dec 2020 |
Year(s) Of Engagement Activity | 2020 |
Description | Visit by Sellafield Staff to discuss Lancaster Spent Fuel Research |
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 | Industry/Business |
Results and Impact | Visit to Lancaster by Sellafield staff to discuss Lancaster's research in spent fuel management. Involved presentations on the manufacture, characterisation and use in corrosion studies of SIMFUELs, the development of MOX SIMFUELs and disposal MOX |
Year(s) Of Engagement Activity | 2022 |
Description | six-weekly meetings with sellafield |
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 | Meetings every 6 weeks with Sellafield and NNL to discuss progress in plutonium storage related research projects |
Year(s) Of Engagement Activity | 2021 |