Behaviour of UK Specific Spent Fuels Under Conditions Relevant to Geological Disposal.

Lead Research Organisation: University of Cambridge
Department Name: Earth Sciences

Abstract

The UK has traditionally reprocessed its nuclear fuel rods to extract and re-use the ~95% uranium and ~ 1% plutonium that remains once they are removed from the reactor. It is becoming clear after reviews by government bodies that some UK nuclear fuels will not now be re-processed and will need to be directly disposed of in a suitable geological repository, recommended as the best option for disposing of the UK's nuclear wastes.

Because of the previous nuclear fuel re-processing policy, very little experimental research has been carried out in the UK on this direct disposal option. However, a large amount has been carried out internationally on fuels that come from pressurised water (PWR) or boiling water reactors (BWR). The nuclear fuels concerned in this proposal are unique to the UK and come from Advanced Gas-cooled Reactors (AGR). These differ in the reactor coolant (carbon dioxide) and the moderator (graphite) from the more common water-moderated reactors used internationally and also in the operating temperature (825 C for AGR compared with ~300 C for a PWR or BWR). These differences create uncertainties in the way that these fuels would behave in a repository when compared with the spent fuels studied internationally.

The aim of this proposal is to bring together researchers from the country's leading research universities and nuclear research universities and both the National Nuclear Laboratory and the Nuclear Decommissioning Authority to build research capacity to investigate the effect of these different fuel characteristics on the fuel behaviour and compare it with that found internationally. The aim is to use the international research underpinned by UK specific research to understand the long term behaviour of spent AGR fuel in repository so contributing to the safety assessment for its disposal.

To do this the project will employ 5 investigators and 6 PhD students to create simulated nuclear fuels that consist of specially prepared uranium dioxide (depleted) with the same microstructural characteristics expected for AGR fuels and the additional chemical components of AGR spent nuclear fuel that result from uranium and plutonium atoms that have fissioned (split) during its time in the reactor. This will be determined by a deep search of UK data on these characteristic microstructures and chemical compositions determined from difficult examinations of the highly radioactive spent fuel in the past.

The team will predict the chemical composition of the fuel for ages between 1,000 and 100,000 years which is thought to span the lifetime of the disposal canisters as they are affected by corrosion. They will then determine the rates of dissolution of the simulated fuels under different water compositions. These would be those expected for some representative natural ground water compositions and to water compositions governed by the dissolution of the steel cladding of the fuel rods and the external containers.

Eventually, uranium minerals will form on the surface of these fuels and they will probably incorporate plutonium and neptunium. The stability of these phases will determine the rate of release of these elements back into the environment and they will be tested for resistance to damage by the radiation that remains at long times into the future.

The group will be guided by an international advisory board and undertake experiments at international facilities equipped for modern analytical methods enabled for work with radioactive samples. This will help establish the group internationally and build the UK capacity for this radiological experimental research so it can support the licensing of a nuclear waste repository in the UK.

Planned Impact

The impact of this programme will be primarily in the creation of a UK experimental research programme on spent nuclear fuel that includes industrial organisations (NNL), government bodies (NDA) and UK research universities. This should have a subsequent impact on the successful implementation of a geological disposal option for advanced gas-cooled reactor (AGR) spent nuclear fuel, which is unique to the UK.

More conventional impact will arise from the documentation of the key outputs of the research. The investigator team has a good track record in publication and in the impact of its papers, reports to industry and input to government policy. We also anticipate the presentation of our work at conferences such as Migration, MRS Scientific Basis of Nuclear Waste Management series, Top Fuel and Global which are the major forums for this work to be discussed.

Further impact will be through a set of networks and personal contacts that have been established by the PI and the team. These are implicit in the proposal through collaborative work with US Department of Energy scientists working at Pacific Northwest National Laboratory and Idaho National Laboratory and European scientists working at EC-JRC Karlsruhe and the Karlsruhe Institute of Technology. The constituent institutions of the investigator team are also members of the EPSRC-funded Nuclear Fission Consortium and the Nuclear Engineering Doctorate Centre (which Imperial leads in collaboration with Manchester). These connections and the personal contacts of the PI and CI's through their participation in EC FP7 programmes such as F-Bridge, FAILFUELS, Archer and Euract-NMR will further the dissemination of UK research on spent nuclear fuel. This will have the impact of enhancing the reputation of the UK in a previously neglected research area and also position us within the EC research community to participate in future EC research consortia.

Ultimately, the research could have a positive effect in re-establishing nuclear power within the UK by contributing to the public perception that spent fuels can be disposed of in a safe way.

Publications

10 25 50
 
Description We have been able to tailor the chemistry and grain structure of a mixture of depleted uranium dioxide and various elements produced by nuclear fission to mimic a spent nuclear fuel. This allows much more sophisticated analysis of the long term behaviour without the complication of working with highly radioactive materials.

We have obtained an unusual result in that irradiated films of UO2 seem to be less soluble (in terms of U) that unirradiated films - at least under oxidising conditions we are now verifying this under reducing conditions.

Under oxidising conditions the solubility of UO2 is extremely low 100-200 parts per trillion (ppt) in solution in dynamic leaching experiments. This increases to 800-1000 ppt for irradiated materials with no clear effect of the incorporated fission products.

TEM sections taken from irradiated UO2 and doped simfuel materials show an increase in dislocations (loops & lines) throughout the peak damage region. The presence of fission products in the UO2 correlates with larger dislocation loops and lines, which is usually attributed to greater defect mobility in other materials with this difference in defect structure. We are understanding the effects of radiation damage in UO2 fuel at the atomistic level.
Exploitation Route Approach beginning to be adopted in EU research programmes.
Sectors Communities and Social Services/Policy,Energy,Environment

URL http://snf.esc.cam.ac.uk
 
Description The use of model UO2 system and simfuels has been adopted by the EC Implementing Geological Disposal Technology Platform to evaluate chemistry in container effects in the DISCO research project (WG4 of IGD-TP work programme). This H2020 proposal was successful and is contract negotiation for June 1st 2017 start. The grant has started and Farnan is a member of the executive committee of H2020 Euratom Grant 75443 DisCo - 'Modern spent fuel dissolution and chemistry in failed container conditions' and a work package leader (WP2) on modelling UO2 spent fuel.
First Year Of Impact 2017
Sector Energy,Environment
Impact Types Policy & public services

 
Description Engineering and Physical Sciences Research Council (EPSRC): - Centres for Doctoral Training (£ 50000; 2018 - 2022)
Amount £5,181,479 (GBP)
Funding ID EP/L015390/1 
Organisation Engineering and Physical Sciences Research Council (EPSRC) 
Sector Public
Country United Kingdom
Start 10/2018 
End 09/2022
 
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 National Nuclear Innovation Programme: Advanced Nuclear Fuel Programme
Amount £2,000,000 (GBP)
Organisation Government of the UK 
Sector Public
Country United Kingdom
Start 07/2018 
End 03/2019
 
Description National Nuclear Laboratory Studentships
Amount £64,000 (GBP)
Funding ID NNL Agreement No 80335803 
Organisation National Nuclear Laboratory 
Sector Public
Country United Kingdom
Start 10/2014 
End 03/2018
 
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 09/2018 
End 09/2022
 
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
 
Title Research data supporting the publication: 'Structural effects in UO$_2$ thin films irradiated with U ions' 
Description Project: PhD work by A.J. Popel: 'The effect of radiation damage by fission fragments on the structural stability and dissolution of the UO2 fuel matrix'. The Excel file 'XRD_UO2_films_YSZ' with raw XRD data supporting Figures 5, 6 and 7 in the publication: A.J. Popel, A.M. Adamska, P.G. Martin, O.D. Payton, G.I. Lampronti, L. Picco, L. Payne, R. Springell, T.B. Scott, I. Monnet, C. Grygiel, I. Farnan, Structural effects in UO2 thin films irradiated with U ions, Nucl. Instr. and Meth. in Phys. Res. B 386 (2016) 8-15, https://doi.org/10.1016/j.nimb.2016.09.019. The XRD analysis was performed to assess crystallographic structure of the as-produced and irradiated thin films of UO2 on YSZ substrates. The data were generated in June-July 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK. A D8 Bruker diffractometer equipped with a primary Ge monochromator for Cu Ka1 and a Sol-X solid state detector operating in standard Bragg-Brentano geometry was used for the analysis. The samples were spun during signal collection and a zero-background sample holder was used in all cases. The data can be accessed through the University of Cambridge Data Repository. 
Type Of Material Database/Collection of data 
Year Produced 2017 
Provided To Others? Yes  
 
Title Research data supporting the publication: 'Structural effects in UO$_2$ thin films irradiated with fission-energy Xe ions' 
Description Project: PhD work by A.J. Popel: 'The effect of radiation damage by fission fragments on the structural stability and dissolution of the UO2 fuel matrix'. The Excel file 'XRD_UO2_films_LSAT' with raw XRD data supporting Figure 10 and XRD results in the publication: A.J. Popel, V.A. Lebedev, P.G. Martin, A.A. Shiryaev, G.I. Lampronti, R. Springell, S.N. Kalmykov, T.B. Scott, I. Monnet, C. Grygiel, I. Farnan, Structural effects in UO2 thin films irradiated with fission-energy Xe ions, J. Nucl. Mater. 482 (2016) 210-217, https://doi.org/10.1016/j.jnucmat.2016.10.024. The XRD analysis was performed to assess crystallographic structure of the as-produced and irradiated thin films of UO2 on LSAT substrates. The data were generated in June-July 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK. A D8 Bruker diffractometer equipped with a primary Ge monochromator for Cu Ka1 and a Sol-X solid state detector operating in standard Bragg-Brentano geometry was used for the analysis. The samples were spun during signal collection and a zero-background sample holder was used in all cases. The data can be accessed through the University of Cambridge Data Repository. 
Type Of Material Database/Collection of data 
Year Produced 2017 
Provided To Others? Yes  
 
Title Research data supporting the publication: 'The effect of fission-energy Xe ion irradiation on dissolution of UO$_2$ thin films' 
Description Project: PhD work by A.J. Popel: 'The effect of radiation damage by fission fragments on the structural stability and dissolution of the UO2 fuel matrix'. The Excel file 'U_ICP-MS data' with output ICP-MS data and calculations for water and acid dilutions supporting Figures 2 and 3 and ICP-MS results in the publication: A.J. Popel, V.G. Petrov, V.A. Lebedev, J. Day, S.N. Kalmykov, R. Springell, T.B. Scott, I. Farnan, The effect of fission-energy Xe ion irradiation on dissolution of UO2 thin films, J. Alloys Compd. 721 (2017) 586-592, https://doi.org/10.1016/j.jallcom.2017.05.084. The ICP-MS analysis was performed to measure 238U concentration in the extracted solutions. The data were generated on the 13-14th of October 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK, on a Perkin Elmer SCIEX Elan DRC II quadrupole ICP-MS. The data can be accessed through the University of Cambridge Data Repository. 
Type Of Material Database/Collection of data 
Year Produced 2017 
Provided To Others? Yes  
 
Title Research data supporting the publication: 'The effect of fission-energy Xe ion irradiation on the structural integrity and dissolution of the CeO$_2$ matrix' 
Description Project: PhD work by A.J. Popel: 'The effect of radiation damage by fission fragments on the structural stability and dissolution of the UO2 fuel matrix'. The Excel file 'XRD_CeO2' with raw XRD data supporting the CeO2 powder XRD results The Text files 'sample1_wt' and 'sample2_wt' with raw EPMA data supporting the EPMA analysis of the two bulk CeO2 samples The Excel file 'ICP-MS data' with output ICP-MS data and calculations for water and acid dilutions supporting Figures 5 and 6 and ICP-MS results in the publication: A.J. Popel, S. Le Solliec, G.I. Lampronti, J. Day, P.K. Petrov, I. Farnan, The effect of fission-energy Xe ion irradiation on the structural integrity and dissolution of the CeO2 matrix, J. Nucl. Mater. 484 (2017) 332-338, https://doi.org/10.1016/j.jnucmat.2016.10.046. The XRD analysis was performed to verify the identity of the as-supplied bulk samples and check for other phases. The data were generated on the 5th of June 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK. A bulk sample of the as-supplied CeO2 was powdered using mortar and pestle and analysed on a D8 Bruker diffractometer equipped with a primary Ge monochromator for Cu Ka1 and a Sol-X solid state detector operating in standard Bragg-Brentano geometry. The sample was spun during signal collection and a zero-background sample holder was used. The EPMA analysis was performed to check the composition of the as-supplied bulk samples. The data were generated on the 3rd of July 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK. Prior to the analysis, the samples were embedded in a resin, polished and carbon coated to ensure conductivity for the analysis using a Cameca SX-100 electron microprobe analyser. Calibration of the equipment was performed using a set of rare earth elements. The ICP-MS analysis was performed to measure 140Ce concentration in the extracted solutions. The data were generated on the 23rd of July 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK, on a Perkin Elmer SCIEX Elan DRC II quadrupole ICP-MS. The data can be accessed through the University of Cambridge Data Repository. 
Type Of Material Database/Collection of data 
Year Produced 2017 
Provided To Others? Yes  
 
Title Research data supporting the publication: 'The effect of fission-energy Xe ion irradiation on the structural integrity and dissolution of the CeO$_2$ matrix' 
Description Project: PhD work by A.J. Popel: 'The effect of radiation damage by fission fragments on the structural stability and dissolution of the UO2 fuel matrix'. The Excel file 'XRD_CeO2' with raw XRD data supporting the CeO2 powder XRD results The Text files 'sample1_wt' and 'sample2_wt' with raw EPMA data supporting the EPMA analysis of the two bulk CeO2 samples The Excel file 'ICP-MS data' with output ICP-MS data and calculations for water and acid dilutions supporting Figures 5 and 6 and ICP-MS results in the publication: A.J. Popel, S. Le Solliec, G.I. Lampronti, J. Day, P.K. Petrov, I. Farnan, The effect of fission-energy Xe ion irradiation on the structural integrity and dissolution of the CeO2 matrix, J. Nucl. Mater. 484 (2017) 332-338, https://doi.org/10.1016/j.jnucmat.2016.10.046. The XRD analysis was performed to verify the identity of the as-supplied bulk samples and check for other phases. The data were generated on the 5th of June 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK. A bulk sample of the as-supplied CeO2 was powdered using mortar and pestle and analysed on a D8 Bruker diffractometer equipped with a primary Ge monochromator for Cu Ka1 and a Sol-X solid state detector operating in standard Bragg-Brentano geometry. The sample was spun during signal collection and a zero-background sample holder was used. The EPMA analysis was performed to check the composition of the as-supplied bulk samples. The data were generated on the 3rd of July 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK. Prior to the analysis, the samples were embedded in a resin, polished and carbon coated to ensure conductivity for the analysis using a Cameca SX-100 electron microprobe analyser. Calibration of the equipment was performed using a set of rare earth elements. The ICP-MS analysis was performed to measure 140Ce concentration in the extracted solutions. The data were generated on the 23rd of July 2014 at the Department of Earth Sciences, University of Cambridge, Cambridge, UK, on a Perkin Elmer SCIEX Elan DRC II quadrupole ICP-MS. The data can be accessed through the University of Cambridge Data Repository. 
Type Of Material Database/Collection of data 
Year Produced 2017 
Provided To Others? Yes  
 
Description NNL collaboration in the area of the management of spent nuclear fuel 
Organisation National Nuclear Laboratory
Country United Kingdom 
Sector Public 
PI Contribution Working with NNL subject matter experts in the area of spent nuclear fuel management and disposal through a series of PhD studentships
Collaborator Contribution Funding of a series of PhD studentships to support Lancaster's work on the management and disposal of spent nuclear fuel
Impact "Corrosion Behaviour of AGR Simulated Fuels - Evolution of the Fuel Surface" N.Rauff-Nisthar, C.Boxall, I.Farnan, Z.Hiezl, W.Lee, C.Perkins, R.J.Wilbraham, in "Corrosion in Nuclear Energy Systems: From Cradle to Grave ", J. J. Noel, R. Newman, D. Shoesmith and S. Fujimoto (Eds.), The Electrochemical Society, Inc., Pennington NJ, Electrochem.Soc.Trans., 53(21) 95-104 (2013) DOI:10.1149/05321.0095ecst "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 "Corrosion Behaviour of AGR SIMFUELS" N.Rauff-Nisthar, C.Boxall, D.Hambley, Z.Hiezl, C.Padovani, R.Wilbraham, in Final Workshop Proceedings of the Collaborative Project "Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel", B.Kienzler, V.Metz, A.Valls (Eds.), KIT Scientific Reports 7716, KIT Scientific Publishing, Karlsruhe, 2015, pp. 295-302, ISBN 978-3-7315-0525-9. DOI: 10.5445/KSP/1000054569 "Corrosion Behaviour of AGR SIMFUELS" N.Rauff-Nisthar, C.Boxall, D.Hambley, Z.Hiezl, W.E.Lee, C.Padovani, R.J.Wilbraham, in "Corrosion General Session", R.Buchheit (Ed.), The Electrochemical Society, Inc., Pennington NJ, Electrochem.Soc.Trans., 66(17) 85-94 (2015) DOI:10.1149/06617.0085ecst "Collaborative Research Programme in Decommissioning, Immobilisation and Storage Solutions for Nuclear Waste Inventories (DISTINCTIVE)", M. Fairweather, S.R. Biggs, A.M.E. Ward, C. Boxall, N.D.M. Evans, J.A. Hriljac, N.C. Hyatt, N. Kaltsoyannis, W.E. Lee, R.J. Lunn, S.M. Pimblott, T.B. Scott, in Waste Management 2016 Conference Proceedings, WM Symposia, Temple, Arizona, 2016, Paper No. 16466, 15 pages, ISBN Number: 978-0-9828171-5-5 "Corrosion of AGR Fuel Pin Steel under Conditions Relevant to Permanent Disposal", C.Anwyl, C.Boxall, R.Wilbraham, D.Hambley and C.Padovani, Procedia Chem., 21, 247-254 (2016). DOI: 10.1016/j.proche.2016.10.035, IF = 0.4 "AGR Cladding Corrosion: Investigation of the Effect of Temperature on Unsensitized Stainless Steel", E.Howett, C.Boxall, D.Hambley 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(11), 615-620 (2017) DOI: 10.1557/adv.2016.651 "The DISTINCTIVE University Consortium: An Overview" M. Fairweather, L. Tovey, C. Boxall, J.A. Hriljac, N.C. Hyatt, N. Kaltsoyannis, W.E. Lee, R.J. Lunn, S.M. Pimblott, D. Read, T.B. Scott in Waste Management 2018 Conference Proceedings, WM Symposia, Temple, Arizona, 2018, Paper No. 18102 "The DISTINCTIVE University Consortium Theme 1: AGR, Magnox and Exotic Spent Fuels" M. Fairweather, L. Tovey, C. Boxall, J.A. Hriljac, N.C. Hyatt, N. Kaltsoyannis, W.E. Lee, R.J. Lunn, S.M. Pimblott, D. Read, T.B. Scott in Waste Management 2018 Conference Proceedings, WM Symposia, Temple, Arizona, 2018, Paper No.18345. "Raman Studies of Advanced Gas-Cooled Reactor Simulated Spent Nuclear Fuels" R.J. Wilbraham, N. Rauff-Nisthar, C. Boxall, E.A. Howett, D.I. Hambley, Z. Hiezl, W.E. Lee, C. Padovani, Prog.Nucl.Sci.Tech, 5, 213-216 (2018). DOI: 10.15669/pnst.5.213 "The Behavior of Advanced Gas Reactor Simulated Spent Nuclear Fuels in Wet Interim Storage Conditions", E.A. Howett, C. Boxall, R.J.Wilbraham, D.I. Hambley, Prog.Nucl.Sci.Tech, 140-143 (2018). DOI: 10.15669/pnst.5.140
Start Year 2011
 
Description Attendance at GLOBAL / TOPFUEL Conference, Seattle 
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 Attending at GLOBAL / TOPFUEL Conference in Seattle. Made a total of 8 presentations to a mixed industry / academic audience. Conference papers arising from those presentations are listed in the publications section
Year(s) Of Engagement Activity 2019
URL http://globaltopfuel.ans.org/
 
Description EPSRC/FCO sponsored visit to Japan 
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 at and involvement in EPSRC/Foreign & Commonwealth Office sponsored workshop in Japan in Feb 2019. Purpose of workshop was to develop joint UK/Japan research projects t support the safe clean up of Fukushima. Future activity will be submission of a proposal to the expected EPSRC/MEXT call in this area
Year(s) Of Engagement Activity 2019
 
Description LRF Conference 
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 Exhibiting at the biannual Lloyd's Register Foundation International conference in London, May 2018
Year(s) Of Engagement Activity 2018
 
Description Lloyds Register Foundation Conference - All Centre Meeting Oct 2019 
Form Of Engagement Activity Participation in an activity, workshop or similar
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Supporters
Results and Impact meeting of the Lloyd's Register Foundation Centre for the Safety of Nuclear Energy - included presentations from participants in TRANSCEND, ATLANTIC, TRIBECA Spent Fuel project
Year(s) Of Engagement Activity 2019
 
Description Meetng with NNL to discuss 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 Meeting with NNL subject matter expert on Spent Nuclear Fuel to discuss progress on associated research programme
Year(s) Of Engagement Activity 2018,2019
 
Description NNL Fuels Project meeting sept 17 
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 Meeting with NNL to update on spent nuclear fuels project
Year(s) Of Engagement Activity 2017
 
Description NNL visit to review RWM work 
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 dave hambley, NNL to discuss progress on RWM/TRANSCEND work
Year(s) Of Engagement Activity 2019
 
Description Visit by NNL to discuss progress in Spent Fuels Research Programme 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Industry/Business
Results and Impact Presentation to and disuccion with NNL on progress in Spent Fuels Research Programme at Lancaster
Year(s) Of Engagement Activity 2018
 
Description actinides - spent fuel in storage talk 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact "The Behaviour of Advanced Gas Reactor Simulated Spent Nuclear Fuels in Wet Interim Storage Conditions", E.Howett, C.Boxall, D.Hambley, R.Wilbraham, Actinides 2017, Tohoku University, Sendai, Japan, 10th - 14th July 2017
Year(s) Of Engagement Activity 2017
 
Description actinides - spent fuel raman talk 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact "XRD and Raman Studies of Advanced Gas Reactor Simulated Spent Nuclear Fuels Under Geological Disposal Conditions", R.Wilbraham, C.Boxall, D.Hambley, Z.Hiezl, W.Lee, C.Padovani, N.Rauff-Nisthar, Actinides 2017, Tohoku University, Sendai, Japan, 10th - 14th July 2017
Year(s) Of Engagement Activity 2017
 
Description chernobyl 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 Invited Lecture "Waste Management and Spent Fuel Research at Lancaster University" C.Boxall, UK / Ukraine GCRF Workshop on Chernobyl Decommissioning, Halifax Hall Hotel, Sheffield, 28th February - 1st March 2017
Year(s) Of Engagement Activity 2017