MIDAS Publications

2024

Microstructure and mechanical performance of cold spray Cr coatings
I. Alakiozidis, C. Hunt, A. D. Smith, M. Maric, Z. Shah, A. Ambard, P. Frankel
Journal of Nuclear Materials,  https://doi.org/10.1016/j.jnucmat.2024.155492

Molecular dynamics simulations of neutron induced collision cascades in Zr — Statistical modelling of irradiation damage and potential applications
B. Barzdajn, C. Race
Computational Materials Science, https://doi.org/10.1016/j.commatsci.2024.113315

Modelling amorphization and dissolution of Zr(Fe,Cr)2 secondary phase precipitates in Zircaloys
J. Robson
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2024.155358

Characterization of the strain rate sensitivity of basal, prismatic and pyramidal slip in Zircaloy-4 using micropillar compression
N. Fang, Y. Liu, F. Giuliani, Y. B. Britton
Materials Science and Engineering: A, https://doi.org/10.1016/j.msea.2024.146802

On the Interaction of Grain-scale and Hydride-scale Stresses in Hydrogen Enriched Zirconium Alloy Nuclear Cladding via combined Discrete Dislocation Plasticity and Crystal Plasticity Finite Element modelling
C. Skamniotis, D. Long, L. Yang, M. Wenman, D. Balint
Mechanics of Materials, https://doi.org/10.1016/j.mechmat.2024.105033

Structure and stability of small self-interstitials clusters in zirconium
C. Sakael, C. Domain, A. Ambard, L. Thuinet, A. Legris
Acta Materialia, https://doi.org/10.1016/j.actamat.2024.119708

Evolution of Zr(Fe,Cr)2 second phase particles in Zircaloy-2 under heavy ion irradiation
K. Lynch, Ö. Koç, G. Greaves, A. Carruthers, M. Maric, M. Preuss, A. Cole-Baker, P. Frankel, J. Robson
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2024.155081

A spatially resolved analysis of dislocation loop and nanohardness evolution in proton irradiated Zircaloys
Ö. Koç, R. Thomas, X.Z. Liang, Z. Hegedüs, U. Lienert, R.W. Harrison, M. Preuss, T. Ungár, P. Frankel
Acta Materialia, https://doi.org/10.1016/j.actamat.2024.119799

Quantifying cracking and strain localisation in a cold spray chromium coating on a zirconium alloy substrate under tensile loading at room temperature
I. Alakiozidis, C. Hunt, R. Thomas, D. Lunt, A. D. Smith, M. Maric, Z. Shah, A. Ambard, P. Frankel
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2024.154899

Fractional densities and character of dislocations in different slip modes from powder diffraction patterns
T.Ungár, G. Ribárik, L. Balogh, R. Thomas, O. Koc, M. Preuss, C. Race, P. Frankel
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2023.154828

2023

Discrete dislocation dynamics simulations of -type prismatic loops in zirconium
D. Hortelano Roig, R. Kumar, D. Balint, E. Tarleton
International Journal of Plasticity, https://doi.org/10.1016/j.ijplas.2023.103802

Breakaway Growth Modeling of Zirconium under Irradiation: The Importance of the Formation of <a>-Loop Layers
C. Sakael, C. Domain, A. Ambard, C. P. Race, L. Thuinet, A. Legris
ASTM Zirconium in the Nuclear industry conference proceedings, https://doi.org/10.1520/STP164520220031

Solute Concentrations in the Matrix of Zirconium Alloys Studied by Atom Probe Tomography
J. Eriksson, D. Mayweg, G. Sundell, H. Andre´n, M. Thuvander
ASTM Zirconium in the Nuclear industry conference proceedings, http://doi.org/10.1520/STP164520220026

Mechanical Behavior of Zircaloy-4 in the Presence of Hydrogen in Solid Solution
F. Fagnoni, A. Colldeweih, S. Binato, J. Wheeler, R. Spolenak, M. Wolff, J. Bertsch, L. Duarte
ASTM Zirconium in the Nuclear industry conference proceedings, http://doi.org/10.1520/STP164520220019

Radial Delayed Hydride Cracking in Irradiated Zircaloy-2 Cladding: Advanced Characterization Techniques
A. Colldeweih, F. Fagnoni, O. Yetik, R. Zubler, P. Trtik, C. Anghel, M. Pouchon, Y. Dai, L. Duarte, J. Bertsch
ASTM Zirconium in the Nuclear industry conference proceedings, http://doi.org/10.1520/STP164520220027

Understanding the Mechanistic Role of Lithium in Accelerated Corrosion of Zirconium Alloys Using Advanced Characterization and Atomistic Simulation
A. Garner, C. Gillen, G. Stephens, P. Styman, S. Armson, J. Robinson, J. Liu, A. Carruthers,  F. Pickering, S. Sherry, C. Chan, M. Fenwick, H. Hulme, S. Ortner, C. Riley, C. Grovenor, P. Frankel, S. Middleburgh, A. Cole-Baker
ASTM Zirconium in the Nuclear industry conference proceedings, http://doi.org/10.1520/STP164520220054

Characterization of Irradiation Damage Using X-Ray Diffraction Line-Profile Analysis
R. Thomas, O. Koc, T. Unga´r, G. Zilahi, Z. Hegedues, U. Lienert, G. Riba´rik, H. Sharma, P. Kenesei, M. Preuss, P. Frankel
ASTM Zirconium in the Nuclear industry conference proceedings, http://doi.org/10.1520/STP164520220056 

Characterization of Hydride Precipitation and Reorientation in Zircaloy-4 at Different Metallurgical States
M. Maric, R. Thomas, T. Unga ́r, G. Zilahi, C. Hunt, D. Lunt, J. Donoghue, K. Lynch, P. Frankel, P. Barberis, F. Bourlier, M. Preuss, P. Shanthraj
ASTM Zirconium in the Nuclear industry conference proceedings, http://doi.org/10.1520/STP164520220051 

Modelling of zirconium growth under irradiation and annealing conditions
C. Sakael, C. Domain, A. Ambard, L. Thuinet, A. Legris
International Journal of Plasticity, https://doi.org/10.1016/j.ijplas.2023.103699

Identification, classification and characterisation of hydrides in Zr alloys
M. Maric, R. Thomas, A. Davis, D. Lunt, J. Donoghue, A. Gholinia, M. De Graef, T. Ungar, P. Barberis, F. Bourlier, P. Frankel, P. Shanthraj, M. Preuss
Scripta Materialia, https://doi.org/10.1016/j.scriptamat.2023.115768

Nanoscale Distribution of Alloying Elements in Optimized ZIRLO Using the Invizo 6000
S. Huang,  L. Tegg,  J. Qu,  L. Yang,  I. McCarroll,  P. Burr, J. Cairney
Microscopy and Microanalysis, https://doi.org/10.1093/micmic/ozad067.298

Exploring the hydride-slip interaction in zirconium alloys
Y. Liu, R. Thomas, C. Hardie, P. Frankel, F. Dunne
Acta Materialia, https://doi.org/10.1016/j.actamat.2023.119388

Characterization of local deformation around hydrides in Zircaloy-4 using conventional and high angular resolution electron backscatter diffraction
R. Birch, J. Douglas, T. Britton
Materials Characterization, https://doi.org/10.1016/j.matchar.2023.112988

Characterising the performance of an ultrawide field-of-view 3D atom probe
L. Tegg, A. Breen, S. Huang, T. Sato, S. Ringer, J. Cairney
Ultramicroscopy, https://doi.org/10.1016/j.ultramic.2023.113826

A microstructure-sensitive analytical solution for short fatigue crack growth rate in metallic materials
D. Long, Y. Liu, W. Wan, F. Dunne
International Journal of Mechanical Sciences, https://doi.org/10.1016/j.ijmecsci.2023.108365

Focused Ion Beam induced hydride formation does not affect Fe, Ni, Cr-clusters in irradiated Zircaloy-2
D. Mayweg, J. Eriksson, O. Bäcke, A. Breen, M. Thuvander
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2023.154444

High compressive loading performance of a complex multi-phase hard-facing alloy explained through a highly elastic silicide phase
R. Thomas, D. Bowden, D. Lunt, D. Stewart, M. Preuss
Materialia, https://doi.org/10.1016/j.mtla.2023.101815

Experimental and modelling evidence for hydrogen trapping at a β-Nb second phase particle and Nb-rich nanoclusters in neutron-irradiated low Sn ZIRLO
B. Jenkins, J. Haley, L. Chen, B. Gault, P. Burr, A. Callow, M. Moody, C. Grovenor
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2023.154755

The role of hydrides and precipitates on the strain localisation behaviour in a zirconium alloy
R. Thomas, D. Lunt, M.D. Atkinson, J. Quinta da Fonseca, M. Preuss, P. Honniball, P. Frankel
Acta Materialia, https://doi.org/10.1016/j.actamat.2023.119327

Characterisation of the strain rate sensitivity of basal, prismatic and pyramidal slip in Zircaloy-4 using micropillar compression
N. Fang, Y. Liu, F. Giuliani, B. Britton
arXiv preprints, https://doi.org/10.48550/arXiv.2303.09600

Multi-length-scale study on the heat treatment response to supersaturated nickel-based superalloys: Precipitation reactions and incipient recrystallisation
Y. Tang, C. Panwisawas, B. Jenkins , J. Liu, Z. Shen, E. Salvati, Y. Gong, J. Ghoussoub, S. Michalik, B. Roebuck, P. Bagot, S. Lozano-Perez, C. Grovenor, M. Moody, A. Korsunsky, D. Collins, R Reed
Additive Manufacturing, https://doi.org/10.1016/j.addma.2023.103389

Detecting irradiation-induced strain localisation on the microstructural level by means of high-resolution digital image correlation
D. Lunt, R. Thomas, D. Bowden, M.T.P. Rigby-Bell, S. de Moraes Shubeita, C. Andrews, T. Lapauw, J. Vleugels, J. Quinta da Fonseca, K. Lambrinou, P. Frankel
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2023.154410

Dislocation density transients and saturation in irradiated zirconium
A.R. Warwick, R. Thomas, M. Boleininger, Ö. Koç, G. Zilahi, G. Ribárik, Z. Hegedues, U. Lienert, T. Ungar, C. Race, M. Preuss, P. Frankel, S.L. Dudarev
International Journal of Plasticity, https://doi.org/10.1016/j.ijplas.2023.103590

Diffusion in undoped and Cr-doped amorphous UO2
M.W. Owen, M.W.D. Cooper, M.J.D. Rushton, A. Claisse, W.E. Lee, S.C. Middleburgh
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2023.154270

Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking
A.W. Colldeweih, M.G. Makowska, O.Tabai, D.F. Sanchez, J. Bertsch
Materialia, https://doi.org/10.1016/j.mtla.2023.101689

The influence of microstructure on short fatigue crack growth rates in Zircaloy-4: Crystal plasticity modelling and experiment
D J. Long, W. Wan, F.P.E. Dunne
International Journal of Fatigue, https://doi.org/10.1016/j.ijfatigue.2022.107385

Untangling competition between epitaxial strain and growth stress through examination of variations in local oxidation
M.S. Yankova, A. Garner, F. Baxter, S. Armson, C. P. Race, M. Preuss, P. Frankel 
Nature Communications, https://doi.org/10.1038/s41467-022-35706-3

2022

Simulation of crystal plasticity in irradiated metals: A case study on Zircaloy-4
C. Hardie, R. Thomas, Y. Liu, P. Frankel, F.P.E. Dunne
Acta Materialia, https://doi.org/10.1016/j.actamat.2022.118361

Validating x-ray line-profile defect analysis using atomistic models of deformed material
C.P. Race, T. Ungar, G. Ribarik
Pre-print, https://doi.org/10.48550/arXiv.2203.13643

A first principles study of zirconium grain boundaries
A.J. Plowman, C.P. Race
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2022.153853

Dislocation modelling of the plastic relaxation and thermal ratchetting induced by zirconium hydride precipitation
L. Reali, D.S. Balint, M.R. Wenman
Journal of the Mechanics and Physics of Solids, https://doi.org/10.1016/j.jmps.2022.104988

Hydrogen Localisation in Metallurgical Samples With High Resolution Secondary Ion Mass Spectrometry (NanoSIMS)
K. Moore, Y. Aboura, C. Jones, D. Martelo, R. Morana, R. Akid, M. Preuss
Microscopy and Microanalysis, https://doi.org/10.1017/S1431927622006432

Preliminary Atom Probe Tomography Evidence for Hydrogen Trapping at a β-Nb Second Phase Particle in a Neutron-irradiated Zirconium Alloy
B.M. Jenkins, J. Haley, M. Meier, M.E. Jones, B. Gault, P.A. Burr, M.P. Moody, C.R.M. Grovenor
Microscopy and Microanalysis, https://doi.org/10.1017/S1431927622006596

Grand Challenges in Nuclear Engineering
S.L. Dudarev
Frontiers in Nuclear Engineering, https://doi.org/10.3389/fnuen.2022.945270

Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding
A. Colldeweih, J. Bertsch
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2022.153737

Characterisation and modelling of micro- and macroscale creep and strain rate sensitivity in Zircaloy-4
Y. Liu, W. Wan, F.P.E. Dunne
Materials Science and Engineering A, https://doi.org/10.1016/j.msea.2022.142981

Delayed hydride cracking in Zircaloy-2 with and without liner at various temperatures investigated by high-resolution neutron radiography
A.W. Colldeweih, F. Fagnoni, P. Trtik, R. Zubler, M.A. Pouchon, J. Bertsch
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2022.153549

Microstructure understanding of high Cr-Ni austenitic steel corrosion in high-temperature steam
Z. Shen, J. Zhang, S. Wu, X. Luo, B.M. Jenkins, M.P. Moody, S. Lozano-Perez, X. Zeng
Acta Materialia, https://doi.org/10.1016/j.actamat.2022.117634

High temperature zirconium alloys for fusion energy
D.J.M. King, A.J. Knowles, D. Bowden, M.R. Wenman, S. Capp, M. Gorley, J. Shimwell, L. Packer, M.R. Gilbert, A. Harte
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.153431

A novel method for radial hydride analysis in zirconium alloys: HAPPy
M. Maric, R. Thomas, J. Nunez-Iglesias, M. Atkinson, J. Bertsch, P. Frankel, C.P. Race, P. Barberis, F. Bourlier, M. Preussa, P. Shanthraj
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2021.153442

APT and TEM study of behaviour of alloying elements in neutron-irradiated zirconium-based alloys
B.M. Jenkins, J. Haley, M.P. Moody, J.M. Hyde, C.R.M. Grovenor
Scripta Materialia https://doi.org/10.1016/j.scriptamat.2021.114323

Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium
V. Podgurschi, D.J.M. King, J. Smutna, J.R. Kermode, M.R. Wenman
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.153394

2021

Untangling competition between epitaxial strain and growth stress through examination of variations in local oxidation
M. Yankova, A. Garner, F. Baxter, S. Armson, C.P. Race, M. Preuss, P. Frankel
In review https://doi.org/10.21203/rs.3.rs-926825/v1

Hydrogen concentration and hydrides in Zircaloy-4 during cyclic thermomechanical loading
Y. Liu, S. ElChamaa, M.R. Wenman, C.M. Davies, F.P.E. Dunne
Acta Materialia https://doi.org/10.1016/j.actamat.2021.117368

The accommodation of lithium in bulk ZrO2
G.F. Stephens, Y.R. Than, W. Neilson, LJ. Evitts, M.R. Wenman, S.T. Murphy, R.W. Grimes, A. Cole-Baker, S. Ortner, N. Gotham, M.J.D. Rushton, W.E. Lee, S.C. Middleburgh
Solid State Ionics https://doi.org/10.1016/j.ssi.2021.115813

Microstructural complexity and dimensional changes in heavily irradiated zirconium
A. R. Warwick, M. Boleininger, S. L. Dudarev
Physical Review Materials https://doi.org/10.1103/PhysRevMaterials.5.113604

Diffusion in doped and undoped amorphous zirconia
M.W. Owen, M. J.D. Rushton, L.J. Evitts, A. Claisse, M. Puide, W.E. Lee, S. C. Middleburgh
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.153108

Plastic relaxation and solute segregation to β-Nb second phase particles in Zr-Nb alloys: A discrete dislocation plasticity study
L. Reali, D.S. Balint, A.P. Sutton, M.R. Wenman
Journal of the Mechanics and Physics of Solids https://doi.org/10.1016/j.jmps.2021.104581

A deep learning based automatic defect analysis framework for in-situ TEM ion irradiations
M. Shen, G. Li, D. Wu, Y. Yaguchi, J.C. Haley, K.G.Field, D. Morgan
Computational Materials Science https://doi.org/10.1016/j.commatsci.2021.110560

Oxide growth and oxygen transport in proton irradiated Zircaloy-4 oxide layers
C. Jones, M. Gass, M. Preuss, K.L.Moore
Corrosion Science https://doi.org/10.1016/j.corsci.2021.109655

PosgenPy: An automated and reproducible approach to assessing the validity of cluster search parameters in Atom Probe Tomography datasets
P. Klupś, D. Haley, A. J. London, H. Gardner, J. Famelton, B.M. Jenkins, J. M. Hyde, P.A.J. Bagot, M.P. Moody
Microscopy and Microanalysis https://doi.org/10.1017/S1431927621012368

Characterisation of microstructural creep, strain rate and temperature sensitivity and computational crystal plasticity in Zircaloy-4
Y. Liu, W. Wan, S. El Chamaa, M.R. Wenman, C.M. Davies, F.P.E. Dunne
Pre-print https://arxiv.org/abs/2109.05333

Nanoscale characterisation of hydrides and secondary phase particles in Zircaloy-4
W. Lu, P. Kontis, S. Wang, R. Birch, M. Wenman, B. Gault, T.B. Britton
Pre-print https://arxiv.org/abs/2109.10955

Modelling precipitate amorphization in Zircaloys
J.D. Robson
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.152944

Photon Irradiation Effects on Oxide Surface Electrochemistry and Oxide Microstructure of Zircaloy 4 in High-Temperature Water
A. Couet, Y. He, K. Terrani, S.A. Armson, P. Frankel, M. Preuss, T. Kim, M. Elbakhshwan, L. He
Proceedings of Zirconium in the Nuclear Industry: 19th International Symposium https://www.astm.org/stp162220190041.html

The Effect of Loading Direction on Slip and Twinning in an Irradiated Zirconium Alloy
R. Thomas, D. Lunt, M. Atkinson, J. Quinta da Fonseca, M. Preuss, F. Barton, J. O'Hanlon, P. Frankel
Proceedings of Zirconium in the Nuclear Industry: 19th International Symposium https://www.astm.org/stp162220190027.html

The Importance of Substrate Grain Orientation on Local Oxide Texture and Corrosion Performance in α-Zr Alloys
S.A. Armson, A. Garner, F. Baxter, C.P. Race, A. Cole-Baker, C. Riley, M. Preuss, P. Frankel
Proceedings of Zirconium in the Nuclear Industry: 19th International Symposium https://www.astm.org/stp162220190057.html

Toward a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterization and Atomistic Simulation
P. Frankel, A. Garner, A. Plowman, S. Hanlon, C. Gillen, A. Phillion, C.P. Race, J. Donoghue,. C. Anghel, A. Ambard, M. Daymond
Proceedings of Zirconium in the Nuclear Industry: 19th International Symposium https://www.astm.org/stp162220190047.html

A Review of Early Findings within the Collaborative Research Programme MUZIC—“Mechanistic Understanding of Zirconium Corrosion”
M. Preuss
Proceedings of Zirconium in the Nuclear Industry: 19th International Symposium https://www.astm.org/stp162220190105.html

High-Resolution Mapping of Light Elements in Zirconium Oxide with SIMS
C. Jones, K. Li, J. Liu, T. Aarholt, M. Gass, K. Moore, M. Preuss, C.R. Grovenor
Proceedings of Zirconium in the Nuclear Industry: 19th International Symposium https://www.astm.org/stp162220190037.html

Size-distribution of irradiation-induced dislocation-loops in materials used in the nuclear industry
T, Ungár, P. Frankel, G. Ribárik, C.P. Race, M. Preuss
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.152945

Effect of sample thinning on strains and lattice rotations measured from Transmission Kikuchi diffraction in the SEM
P.S. Karamche, N. Saravanan, J.C.Haley, A.J.Wilkinson, S. Lozano-Perez
Ultramicroscopy https://doi.org/10.1016/j.ultramic.2021.113267

Characterizing dislocation loops in irradiated polycrystalline Zr alloys by X-ray line profile analysis of powder diffraction patterns with satellites
T. Ungár, G. Ribárik, M. Topping, R. M. A. Jones, X.D. Xu, R. Hulse, A. Harte, G. Tichy, C. P. Race, P. Frankel, M. Preuss
Journal of Applied Crystallography https://doi.org/10.1107/S1600576721002673

Depth-profiling of residual stress and microstructure for austenitic stainless steel surface treated by cavitation, shot and laser peening
M. Kumagaia, M.E.Curd, H. Soyama, T. Ungár, G. Ribárik, P.J.Withers
Materials Science and Engineering: A https://doi.org/10.1016/j.msea.2021.141037

A fast efficient multi-scale approach to modelling the development of hydride microstructures in zirconium alloys
M. Patel, L. Reali, A.P. Sutton, D.S. Balint, M.R. Wenman
Computational Materials Science https://doi.org/10.1016/j.commatsci.2021.110279

Hydride growth mechanism in zircaloy-4: Investigation of the partitioning of alloying elements
I. Mouton, Y. Chang, P. Chakraborty, S. Wang, L.T. Stephenson, T.B. Britton, B. Gault
Materialia https://doi.org/10.1016/j.mtla.2021.101006

Evidence of hydrogen trapping at second phase particles in zirconium alloys
C. Jones, V. Tuli, Z. Shah, M. Gass, P. A. Burr, M. Preuss, K.L. Moore
Scientific Reports https://doi.org/10.1038/s41598-021-83859-w

Plasticity of zirconium hydrides: a coupled edge and screw discrete dislocation model
L. Reali, M.R. Wenman, A.P. Sutton, D.S. Balint
Journal of the Mechanics and Physics of Solids https://doi.org/10.1016/j.jmps.2020.104219

Microstructural fracture mechanics: Stored energy density at fatigue cracks
Y. Xu, W. Wan, F.P.E. Dunne
Journal of the Mechanics and Physics of Solids https://doi.org/10.1016/j.jmps.2020.104209