Imperial College London

Professor WE (Bill) Lee FREng

Faculty of EngineeringInstitute for Security Science & Technology

Distinguished Research Fellow
 
 
 
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Contact

 

+44 (0)20 7594 6733w.e.lee Website

 
 
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Assistant

 

Ms Denise McGurk +44 (0)20 7594 8864

 
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Location

 

Central LibrarySouth Kensington Campus

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Summary

 

Publications

Publication Type
Year
to

459 results found

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

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

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

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

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

Al Nasiri N, Patra N, Pezoldt M, Colas J, Lee WEet al., 2019, Investigation of a single-layer EBC deposited on SiC/SiC CMCs: Processing and corrosion behaviour in high-temperature steam, Journal of the European Ceramic Society, Vol: 39, Pages: 2703-2711, ISSN: 0955-2219

Two rare earth monosilicates (Yb 2 SiO 5 , and Lu 2 SiO 5 ) were deposited using a low-cost coating application method to produce a single-layer coating. RE- oxides slurries were dip coated on oxidised CMC samples and subsequently heat treated at high temperature to ensure reaction between SiO 2 and RE-oxides to form the RE-monosilicate. A single, continuous, homogeneous thick coating of 25 μm was obtained. X-ray diffraction (XRD) confirmed formation of, RE-monosilicates in Yb and Lu silicate systems. Coated samples were exposed to 90% H 2 O static steam environment at 1350 °C for 25, 50, 100, and 150 h. Scanning Electron Microscopy (SEM) indicated that both coatings adhered strongly to the substrate. Coating thickness reduced from 22 μm to 11 μm for Yb-coating and 13 to 4 μm for Lu-coating with increasing corrosion time from 25 to 150 h, however there was no significant attack of the CMC for all steam exposure times.

Journal article

Rushton MJD, Ipatova I, Evitts LJ, Lee WE, Middleburgh SCet al., 2019, Stoichiometry deviation in amorphous zirconium dioxide, RSC ADVANCES, Vol: 9, Pages: 16320-16327, ISSN: 2046-2069

Journal article

Zhang H, Jayaseelan DD, Bogomol I, Reece MJ, Hu C, Grasso S, Lee WEet al., 2019, A novel microstructural design to improve the oxidation resistance of ZrB2-SiC ultra-high temperature ceramics (UHTCs), JOURNAL OF ALLOYS AND COMPOUNDS, Vol: 785, Pages: 958-964, ISSN: 0925-8388

Journal article

Gasparrini C, Podor R, Fiquet O, Horlait D, May S, Wenman MR, Lee WEet al., 2019, Uranium carbide oxidation from 873 K to 1173 K, Corrosion Science, Vol: 151, Pages: 44-56, ISSN: 0010-938X

Oxidation of UC was studied from 873 to 1173 K in air and in 10 Pa oxygen using a High Temperature Environmental SEM (HT-ESEM). Conversion to U 3 O 8 improved when using 873 K as the oxide product was a fine powder. At higher temperatures (973 K to 1173 K) oxidation slowed due to a densification process with formation of coarse fragments. The oxide fragmentation at 973 K and 1073 K and oxide pulverisation at 873 K were observed in situ in a HT-ESEM. Cracking induced fragmentation and pulverisation was linked to stresses generated from the volumetric transformation from UC to U 3 O 8 .

Journal article

Middleburgh SC, Lee WE, Rushton MJD, 2019, Ceramics in the nuclear fuel cycle, Advanced Ceramics for Energy Conversion and Storage, Pages: 63-87, ISBN: 9780081027264

Ceramics have played a vital role in the rise of nuclear power since its inception in the mid-20th century. Their development and improved understanding are still driving improvements in the safety, efficiency, and reliability of nuclear power (where it remains the leading source of low carbon energy) and these are having beneficial knock-on effects related to nuclear power’s economic benefits. In this chapter, we discuss the leading fuel concepts starting with uranium dioxide (discussing its manufacture and operation), as well as considering the potential advanced fuels including the so-called accident tolerant fuel candidate materials. Ceramics used to improve fuel cycle costs (e.g., burnable absorbers), ceramics formed or applied as protective barriers reducing corrosion and moderating ceramics are also discussed. Finally, a section on nuclear waste management is provided highlighting the pivotal role of ceramic and glassy waste forms.

Book chapter

Giorgi E, Grasso S, Zapata-Solvas E, Lee WEet al., 2018, Reactive carbothermal reduction of ZrC and ZrOC using Spark Plasma Sintering, ADVANCES IN APPLIED CERAMICS, Vol: 117, Pages: S34-S47, ISSN: 1743-6753

Journal article

Pletser D, Ohashi T, Yoshii Y, Lee WEet al., 2018, Temperature dependent volatilisation behaviour of Cs from two commercial adsorbents used at Fukushima measured using novel experimental apparatus, PROGRESS IN NUCLEAR ENERGY, Vol: 109, Pages: 214-222, ISSN: 0149-1970

Journal article

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