Imperial College London

Professor WE (Bill) Lee FREng

Faculty of EngineeringInstitute for Security Science & Technology

Distinguished Research Fellow
 
 
 
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Contact

 

w.e.lee Website

 
 
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Assistant

 

Miss Eva Konstantara +44 (0)20 7594 8864

 
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Location

 

Abdus Salam LibrarySouth Kensington Campus

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Summary

 

Publications

Publication Type
Year
to

466 results found

Owen MW, Rushton MJD, Cooper MWD, Ghardi EM, Claisse A, Lee WE, Middleburgh SCet al., 2023, Modelling the impact of configurational entropy on the stability of amorphous SiO<inf>2</inf>, Scripta Materialia, Vol: 233, ISSN: 1359-6462

Configurational entropy has been computed to assess its impact on stabilizing the amorphous structure of SiO2. Using a range of atomic scale modelling methods, the structure of crystalline and amorphous SiO2 has been assessed and the configurational entropy associated with the structures observed at varying temperatures has allowed computation of the associated Shannon entropy. Combined with the enthalpy terms generated from density functional theory, a robust method for assessing the stability of crystalline and amorphous structures has been presented that can be used in future work assessing the role of dopants, glass forming additions and radiation damage. Future work will include the vibrational entropy term, to capture the full entropic contribution to amorphisation.

Journal article

Owen MW, Cooper MWD, Rushton MJD, Claisse A, Lee WE, Middleburgh SCet al., 2023, Diffusion in undoped and Cr-doped amorphous UO<inf>2</inf>, Journal of Nuclear Materials, Vol: 576, ISSN: 0022-3115

UO2 fuel pellets are often doped with chromium oxide to obtain favourable properties such as higher density, improved thermal stability, large grain sizes, improved pellet-clad interaction margins, and increased fission gas retention during transients. Chromium has a low solubility limit in UO2, with past experimental work reporting solubility limits ranging between 0.004 to 0.06 wt.% Cr. Due to its low solubility, segregation of Cr ions to the grain boundary may occur. Further, the complexity of these boundaries may be high as observed in other ceramics resulting in disordered or amorphous regions along the boundary, affecting a range of material and operational properties of the fuel pellet. To assess these disordered regions, in this work we study amorphous undoped and Cr doped UO2 systems (containing 10–50 at.% Cr3+) that have been modelled using classical molecular dynamics methods incorporating Cr3+ into the well-used CRG potential library. Diffusion coefficients, pre-exponential factors, and activation energies for diffusion were computed for oxygen ions, assessing the impact of structure and extrinsic species on migration. Oxygen diffusion was observed to be much faster in the undoped amorphous system compared to its crystalline counterpart. Oxygen diffusion in doped systems decreased with increasing Cr concentration, highlighting the importance of additives to retain fission products and other migratory species.

Journal article

Middleburgh SC, Dumbill S, Qaisar A, Vatter I, Owen M, Vallely S, Goddard D, Eaves D, Puide M, Limbäck M, Lee WEet al., 2023, Enrichment of Chromium at Grain Boundaries in Chromia Doped UO<inf>2</inf>, Journal of Nuclear Materials, Vol: 575, ISSN: 0022-3115

Assessment of grain boundaries in chromia (Cr2O3) doped fuels has been carried out using high resolution transmission electron microscopy to assess the structure compared to undoped fuel produced via the same process. Chemical analysis of the grain boundary was carried out using Energy Dispersive X-ray Spectroscopy (EDS). It was shown that a relatively disordered phase is formed along the grain boundaries in the doped fuel and that they were chemically enriched in chromium. This has implications for the prediction and understanding of fuel manufacture and in-reactor behaviour as many processes are highly dependant on grain boundary mechanisms.

Journal article

Makurunje P, Middleburgh SC, Lee WE, 2023, Addressing high processing temperatures in reactive melt infiltration for multiphase ceramic composites, Journal of the European Ceramic Society, Vol: 43, Pages: 183-197, ISSN: 0955-2219

Approaches for addressing the high processing temperatures required in reactive melt infiltration (RMI) processing of state-of-the-art multiphase ceramic matrix composites (CMCs) are reviewed. Ultra-high temperature ceramic composites can be realised by reactive melt infiltration of silicon, transition metals and/or alloys designed as immiscible phases, miscible phases, silicide phases and/or silicide eutectics to lower the temperature required for RMI. Whether carbides, borides or nitrides are envisaged in the resultant ceramic matrix composite, RMI presents an optimization challenge of balancing the composition of the phases incorporated and the processing temperature to be used. Current efforts aim at preparing complex and homogeneous microstructure preforms prior to RMI, minimising damage to reinforcing phases, applying rapid heating techniques, and developing in situ real-time monitoring systems during RMI. Future opportunities include integration of additive manufacturing and RMI, the increased use of process modelling and the application of in situ alongside in operando characterization techniques.

Journal article

Lin-Vines AX, Wilson JA, Fraile A, Evitts LJ, Rushton MJD, Astbury JO, Lee WE, Middleburgh SCet al., 2022, Defect behaviour in the MoNbTaVW high entropy alloy (HEA), Results in Materials, Vol: 15

The intrinsic defect formation in the MoNbTaVW HEA is investigated using atomic scale modelling, the goal being to assess its response to radiation damage in its possible use as plasma facing material for fusion reactors. When interstitial defects were modelled, a strong preference to form split interstitial defects containing vanadium was observed, even forming when other interstitial elements were initially placed into the structure. Vacancies and Frenkel pair formation are also modelled and discussed. The distinct behaviour of defects in this HEA has implications for this system as well as related HEAs and their use in nuclear components.

Journal article

Bolukbasi MJ, Middleburgh SC, Vrtiska S, Lee WEet al., 2022, Effect of ZrB2 and UB2 Discrete Burnable Absorber Pins on fuel reactivity, PROGRESS IN NUCLEAR ENERGY, Vol: 150, ISSN: 0149-1970

Journal article

Quadling A, Lee WE, Astbury J, 2022, Materials challenges for successful roll-out of commercial fusion reactors, JOURNAL OF PHYSICS-ENERGY, Vol: 4, ISSN: 2515-7655

Journal article

Wilson JA, Evitts LJ, Fraile A, Wilson RE, Rushton MJD, Goddard DT, Lee WE, Middleburgh SCet al., 2022, Predicting the thermal expansion of body-centred cubic (BCC) high entropy alloys in the Mo-Nb-Ta-Ti-W system, JOURNAL OF PHYSICS-ENERGY, Vol: 4, ISSN: 2515-7655

Journal article

Moore CM, Wilson JA, Rushton MJD, Lee WE, Astbury JO, Middleburgh SCet al., 2022, Hydrogen accommodation in the TiZrNbHfTa high entropy alloy, ACTA MATERIALIA, Vol: 229, ISSN: 1359-6454

Journal article

Mahalle G, Davis TP, Lee WE, Al Mamun Aet al., 2022, Investigation of strain-rate sensitivity of T91 Steel Using Small Punch Testing, Pages: 570-577

The Small Punch Test (SPT) is a useful technique for deriving location-dependent mechanical properties using small-sized specimens. In this work, we have investigated the tensile and fracture behavior of T91 steel, a candidate material for fusion and Gen IV fission nuclear reactors, by the SPT technique. Firstly, the hot shear flow behavior of T91 steel was investigated by SPT in the temperature range of 400-550 ºC under quasi-static strain rates (0.003 mm/min and 0.3 mm/min). Further, the hot deformation material parameters in the exponential power-law and hyperbolic sine constitutive equations have been evaluated. The effect of temperature and strain rate variation on stress exponent in power-law and activation energy from hyperbolic sine equation have been correlated.

Conference paper

Aamoth B, Lee WE, Ahmed H, 2022, Net-Zero Through Small Modular Reactors-Cybersecurity Considerations

In recent years, countries across the world have started developing small modular reactors (SMRs), nuclear reactors that generally produce around 300 megawatts of electricity (MWe). Many believe this type of reactor could be key in helping countries achieve their net-zero goals, as they are theoretically less expensive and safer than their larger counterparts, which usually produce more than 500 MWe. SMRs will be assembled in factories and operated in a mostly remote manner, raising concerns about cybersecurity. This paper attempts to analyze the cybersecurity of traditional nuclear reactors and the cyberphysical systems they rely on, analyze the novel ways in which SMRs will be developed and operated, and then highlight how and why SMRs could be particularly vulnerable to cyber-attacks. This paper finds that SMRs will be more susceptible to cyberattacks when compared to larger, more traditional reactors. Mitigations are offered that should increase the cyber-resilience of SMRs.

Conference paper

Jayaseelan DD, Pramana S, Grasso S, Bai Y, Skinner S, Reece MJ, Lee WEet al., 2021, Fabrication and characterisation of single-phase Hf2Al4C5 ceramics, Journal of the European Ceramic Society, Vol: 42, Pages: 1292-1301, ISSN: 0955-2219

Single-phase Hf2Al4C5 ternary carbide was fabricated from Hf/Al/C powder mixtures by pressure assisted sintering techniques such as hot pressing and spark plasma sintering at 1900 °C for 3 h and 10 min, respectively. XRD confirmed that the ternary carbide started to form at temperatures as low as 1500 °C and with total formation of Hf2Al4C5 after reactive sintering for 1 h at 1900 °C. It is evident from HRTEM that two Hf-C layers were sandwiched with 4 Al-C layers (Al4C3) in the Hf2Al4C5 ternary carbide. Tight interlocking of grains, faceted grains and stacking faults were occasionally observed. Thermal conductivity of Hf2Al4C5 is measured to be 14 w m−1k−1 from room temperature to 1300 °C. The oxidation studies carried out at 1300 °C for 3 h reveal that the oxidation layer thickness is around 220 μm and it contains microcracks closer to sample surface whereas the interface looks seamless without any cracking or spallation of the oxide layer.

Journal article

Stephens GF, Than YR, Neilson W, Evitts LJ, Wenman MR, Murphy ST, Grimes RW, Cole-Baker A, Ortner S, Gotham N, Rushton MJD, Lee WE, Middleburgh SCet al., 2021, The accommodation of lithium in bulk ZrO2, SOLID STATE IONICS, Vol: 373, ISSN: 0167-2738

Journal article

Owen MW, Rushton MJD, Evitts LJ, Claisse A, Puide M, Lee WE, Middleburgh SCet al., 2021, Diffusion in doped and undoped amorphous zirconia, JOURNAL OF NUCLEAR MATERIALS, Vol: 555, ISSN: 0022-3115

Journal article

Zapata-Solvas E, Malmal Moshtaghioun B, Gomez-Garcia D, Dominguez-Rodriguez A, Lee WEet al., 2021, HfB2 ceramic polycrystals: A low-temperature metal-like ceramic at high temperatures?, SCRIPTA MATERIALIA, Vol: 203, ISSN: 1359-6462

Journal article

Bolukbasi MJ, Middleburgh SC, Dahlfors M, Lee WEet al., 2021, Performance and economic assessment of enriched gadolinia burnable absorbers, PROGRESS IN NUCLEAR ENERGY, Vol: 137, ISSN: 0149-1970

Journal article

Evitts LJ, Gilbert MR, Middleburgh SC, Lee WE, Dahlfors Met al., 2021, Utilizing neutronics modelling to predict changing Pu ratios in UO2 in the presence of Th, PROGRESS IN NUCLEAR ENERGY, Vol: 137, ISSN: 0149-1970

Journal article

Ji J, Zhang L, Yu J, Lee WE, Middleburgh SC, Li D, Wang X, Li Q, Wang Z, Shi G, Chen Fet al., 2021, Interface properties of Ti3SiC2/Al2O3 ceramics: Combined experiments and first-principles calculations, CERAMICS INTERNATIONAL, Vol: 47, Pages: 6409-6417, ISSN: 0272-8842

Journal article

Middleburgh SC, Lee WE, Rushton MJD, 2021, Structure and properties of amorphous uranium dioxide, ACTA MATERIALIA, Vol: 202, Pages: 366-375, ISSN: 1359-6454

Journal article

Humphry-Baker SA, Ramanujam P, Smith GDW, Binner J, Lee WEet al., 2020, Ablation resistance of tungsten carbide cermets under extreme conditions, International Journal of Refractory Metals and Hard Materials, Vol: 93, ISSN: 0263-4368

A cobalt-free tungsten carbide cermet (WC-FeNi) has been subjected to oxyacetylene flame tests to simulate extreme operating conditions such as a worst-case fusion reactor accident. In such an accident, air-ingress to the reactor may impinge on components operating at surface temperatures in excess of 1000 °C, leading to tungsten oxide formation and its subsequent hazardous volatilisation. Here, the most challenging accident stage has been simulated, where the initial air-ingress could lead to extremely rapid air-flow rates. These conditions were simulated using an oxidising oxyacetylene flame. The separation between flame nozzle and sample was varied to permit peak surface temperatures of ~950–1400 °C. When the peak temperature was below 1300 °C, the cermet gained mass due to the dominance of oxide scale formation. Above 1300 °C, the samples transitioned into a mass loss regime. The mass loss regime was dominated by ablation of the scale rather than its volatilisation, which was confirmed by performing a systematic thermogravimetric kinetic analysis. The result was unexpected as in other candidate shielding materials, e.g. metallic tungsten, volatilisation is considered the primary dispersion mechanism. The unusual behaviour of the cermet scale is explained by its relatively low melting point and by the lower volatility of its FeWO4 scale compared to tungsten's WO3 scale. The substantially lower volatility of the WC cermet scale compared to metallic W indicates it may have a superior accident tolerance.

Journal article

Fossati PCM, Mellan TA, Kuganathan N, Lee WEet al., 2020, Atomistic modeling approach to the thermodynamics of sodium silicate glasses, JOURNAL OF THE AMERICAN CERAMIC SOCIETY, Vol: 104, Pages: 1331-1344, ISSN: 0002-7820

Journal article

Roumiguier L, Antou G, Pradeilles N, Jankowiak A, Zapata-Solvas E, Lee WE, Maitre Aet al., 2020, Effect of powder purification by heat-treatment on the creep behaviour of dense boron carbide monoliths, JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, Vol: 40, Pages: 2253-2259, ISSN: 0955-2219

Journal article

Gasparrini C, Rana D-S, Le Brun N, Horlait D, Markides C, Farnan I, Lee Wet al., 2020, On the stoichiometry of zirconium carbide, Scientific Reports, Vol: 10, ISSN: 2045-2322

The dependencies of the enhanced thermomechanical properties of zirconium carbide (ZrCx) with sample purity and stoichiometry are still not understood due to discrepancies in the literature. Multiple researchers have recently reported a linear relation between the carbon to zirconium atomic ratio (C/Zr) and the lattice parameter, in contrast with a more established relationship that suggests that the lattice parameter value attains a maximum value at a C/Zr ~ 0.83. In this study, the relationship between C/Zr atomic ratio and the lattice parameter is critically assessed: it is found that recent studies reporting the thermophysical properties of ZrCx have unintentionally produced and characterised samples containing zirconium oxycarbide. To avoid such erroneous characterization of ZrCx thermophysical properties in the future, we propose a method for the accurate measurement of the stoichiometry of ZrCx using three independent experimental techniques, namely: elemental analysis, thermogravimetric analysis and nuclear magnetic resonance spectroscopy. Although a large scatter in the results (ΔC/Zr = 0.07) from these different techniques was found when used independently, when combining the techniques together consistent values of x in ZrCx were obtained.

Journal article

Rana D-SBK, Solvas EZ, Lee WE, Farnan Iet al., 2020, An investigation of the long-range and local structure of sub-stoichiometric zirconium carbide sintered at different temperatures, SCIENTIFIC REPORTS, Vol: 10, ISSN: 2045-2322

Journal article

Middleburgh SC, Ipatova I, Evitts LJ, Rushton MJD, Assinder B, Grimes RW, Lee WEet al., 2020, Evidence of excess oxygen accommodation in yttria partially-stabilized zirconia, Scripta Materialia, Vol: 175, Pages: 7-10, ISSN: 1359-6462

Yttria partially stabilized zirconia (ZrO2)x(Y2O3)½-x has been investigated to understand accommodation of excess oxygen into its structure. ZrO2 powder with 8 wt% Y2O3 additions was treated in 30 vol% H2O2 solution to promote oxidation of the material. A new Raman peak was observed after treatment at 840 cm−1, consistent with previous reports of solid state peroxide ions (O22−). This was corroborated using atomic scale simulation based on density functional theory; these also highlighted the near-zero solution enthalpy for excess oxygen in the monoclinic structure via the formation of a peroxide ion defect.

Journal article

Bowden D, Ward J, Middleburgh S, Shubeita SDM, Zapata-Solvas E, Lapauw T, Vleugels J, Lambrinou K, Lee WE, Preuss M, Frankel Pet al., 2020, The stability of irradiation-induced defects in Zr3AlC2, Nb4AlC3 and (Zr-0.5,Ti-0.5)(3)AlC2 MAX phase-based ceramics, ACTA MATERIALIA, Vol: 183, Pages: 24-35, ISSN: 1359-6454

Journal article

Evitts LJ, Middleburgh SC, Kardoulaki E, Ipatova I, Rushton MJD, Lee WEet al., 2020, Influence of boron isotope ratio on the thermal conductivity of uranium diboride (UB2) and zirconium diboride (ZrB2), JOURNAL OF NUCLEAR MATERIALS, Vol: 528, ISSN: 0022-3115

Journal article

Dahlfors M, Joannou J, Brummitt A, Rushton MJD, Middleburgh SC, Lee WEet al., 2020, The UK national thermal-hydraulics facility: Motivations, design and planning status, Pages: 2876-2886

A UK National Thermal-Hydraulics Facility (NTHF) dedicated to supporting new reactor and other relevant business is being developed, one of the purposes being to deliver on the government's carbon emission reduction commitments. The facility site is foreseen to be at Menai Science Park on the isle of Anglesey in North Wales, a region expected to see significant low carbon energy deployment in coming years. The UK NTHF is envisioned to cater for the needs of emerging nuclear in the UK - but also to serve as a hardware platform for international thermal-hydraulics research collaboration. Plans are to construct a platform capable of maintaining several test loops including support for the UK's on-going, conventional nuclear new build programme as well as Gen-IV systems and associated materials like molten salt and liquid metal coolant media. Motivations are given for NTHF expected capabilities and requirements, which form the basis for its current design and planning state.

Conference paper

Hsieh Y-H, Rushton MJD, Fossati PCM, Lee WEet al., 2020, Thermal footprint of a geological disposal facility containing EURO-GANEX wasteforms, PROGRESS IN NUCLEAR ENERGY, Vol: 118, ISSN: 0149-1970

Journal article

Juthapakdeeprasert J, Diaz OG, Lerdprom W, Meneses DDS, Jayaseelan DD, Lee WEet al., 2019, Reactions and emissivity of cerium oxide with phosphate binder coating on basic refractory brick, INTERNATIONAL JOURNAL OF APPLIED CERAMIC TECHNOLOGY, Vol: 17, Pages: 668-676, ISSN: 1546-542X

Journal article

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