MIDAS Publications

2024

KC 4
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

KC 1
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

KC 1 & 3
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

KC 2 & 4
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

KC 2 & 4
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

KC 1
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

KC 1
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

KC 1 & 2
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

KC 2 & 4
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

KC 1
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

KC 2
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

KC 1
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

KC 1 & 3
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

KC 4
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

KC 4
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

KC 3
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

KC 1
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 

KC 4
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 

KC 1
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

KC 3 & 4
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

KC 2 & 4
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

KC 2
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

KC 1 & 4
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

KC 2
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

KC 2 & 4
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

KC 1 & 4
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

KC 1 & 4
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

KC 1
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

KC 2 & 4
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

KC 2 & 4
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

KC 2
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

KC 1
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

KC 3
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

KC 4
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

KC 4
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

KC 3
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

KC 1 & 2
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

KC 2
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

KC 4
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

KC 4
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

KC 4
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

KC 1 & 4
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

KC 4
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

KC 2 & 4
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

KC 1 & 4
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

KC 3
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

KC 4
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

KC 1
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

KC 3 & 4
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

KC 3
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

KC 2 & 4
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

KC 3
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

KC 1
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

KC 3
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

KC 2
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

KC 1
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

KC 3
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

KC 1
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

KC 2
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

KC 1
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

KC 4
Modelling precipitate amorphization in Zircaloys
J.D. Robson
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.152944

KC 3
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

KC 1 & 2
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

KC 3
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

KC 4
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

KC 3
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

KC 3
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

KC 1
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

KC 2 & 4
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

KC 1
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

KC 4
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

KC 4
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

KC 3 & 4
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

KC 2 & 4
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

KC 2 & 4
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