MIDAS KC4 PUBLICATIONS
2024
Improved understanding of the growth of blocky alpha in welded Zircaloy-4 (KC4)
Birch R.M, B.T. Britton
Acta Materialia, https://www.sciencedirect.com/science/article/pii/S1359645424005020#ack0001
Microstructure and mechanical performance of cold spray Cr coatings (KC 4)
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 (KC 4)
B. Barzdajn, C. Race
Computational Materials Science, https://doi.org/10.1016/j.commatsci.2024.113315
Characterization of the strain rate sensitivity of basal, prismatic and pyramidal slip in Zircaloy-4 using micropillar compression (KC 2 & 4)
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 (KC 2 & 4)
C. Skamniotis, D. Long, L. Yang, M. Wenman, D. Balint
Mechanics of Materials, https://doi.org/10.1016/j.mechmat.2024.105033
Quantifying cracking and strain localisation in a cold spray chromium coating on a zirconium alloy substrate under tensile loading at room temperature (KC 2 & 4)
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
2023
Mechanical Behavior of Zircaloy-4 in the Presence of Hydrogen in Solid Solution (KC 4)
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 (KC 4)
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
Characterization of Hydride Precipitation and Reorientation in Zircaloy-4 at Different Metallurgical States (KC 4)
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
Identification, classification and characterisation of hydrides in Zr alloys (KC 3 & 4)
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 (KC 2 & 4)
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
Characterization of local deformation around hydrides in Zircaloy-4 using conventional and high angular resolution electron backscatter diffraction (KC 1 & 4)
R. Birch, J. Douglas, T. Britton
Materials Characterization, https://doi.org/10.1016/j.matchar.2023.112988
A microstructure-sensitive analytical solution for short fatigue crack growth rate in metallic materials (KC 2 & 4)
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 (KC 1 & 4)
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 (KC 1 & 4)
R. Thomas, D. Bowden, D. Lunt, D. Stewart, M. Preuss
Materialia, https://doi.org/10.1016/j.mtla.2023.101815
The role of hydrides and precipitates on the strain localisation behaviour in a zirconium alloy (KC 2 & 4)
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 (KC 2 & 4)
N. Fang, Y. Liu, F. Giuliani, B. Britton
arXiv preprints, https://doi.org/10.48550/arXiv.2303.09600
Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking (KC 4)
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 (KC 4)
D J. Long, W. Wan, F.P.E. Dunne
International Journal of Fatigue, https://doi.org/10.1016/j.ijfatigue.2022.107385
2022
A first principles study of zirconium grain boundaries (KC 4)
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 (KC 4)
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) (KC 4)
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 (KC 1 & 4)
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
Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding (KC 4)
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 (KC 2 & 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 (KC 1 & 4)
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
A novel method for radial hydride analysis in zirconium alloys: HAPPy (KC 4)
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
Atomistic modelling of iodine-oxygen interactions in strained sub-oxides of zirconium (KC 3 & 4)
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
Hydrogen concentration and hydrides in Zircaloy-4 during cyclic thermomechanical loading (KC 2 & 4)
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
Modelling precipitate amorphization in Zircaloys (KC 4)
J.D. Robson
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2021.152944
Toward a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterization and Atomistic Simulation (KC 4)
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 fast efficient multi-scale approach to modelling the development of hydride microstructures in zirconium alloys (KC 4)
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 (KC 4)
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 (KC 3 & 4)
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 (KC 2 & 4)
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 (KC 2 & 4)
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
2020
Predicting crack patterns in SiC-based cladding for LWR applications using peridynamics (KC 4)
A. Bamgboye, T.A. Haynes, M.R. Wenman
Procedia Structural Integrity https://doi.org/10.1016/j.prostr.2020.10.125
Slip–hydride interactions in Zircaloy-4: Multiscale mechanical testing and characterisation (KC 2 & 4)
S. Wang, F. Giuliani, T.B. Britton
Acta Materialia https://doi.org/10.1016/j.actamat.2020.09.038
Characterisation of deuterium distributions in corroded zirconium alloys using high-resolution SIMS imaging (KC 3 & 4)
J.Liu. K. Li, J. Sayers, T. Aarholt, G. He, H. Hulme, A. Garner, M. Preuss, H. Nordin, J.M. Partezana, M.L. Limbäck, S. Lozano-Perez, S. Ortner, C.R.M. Grovenor
Acta Materialia https://doi.org/10.1016/j.actamat.2020.09.040
Investigating iodine-induced stress corrosion cracking of zirconium alloys using quantitative fractography (KC 4)
C. Gillen, A. Garner, C. Anghel, P. Frankel
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2020.152272
Deformation and fracture of zirconium hydrides during the plastic straining of Zr-4 (KC 2 & 4)
L. Reali, S. El Chamaa, D.S. Balint, C.M. Davies, M.R. Wenman
MRS Advances https://doi.org/10.1557/adv.2020.145
A first principles study of zirconium grain boundaries (KC 4)
A. J. Plowman, C. P. Race
Pre-print https://arxiv.org/abs/2009.05347
Microstructure-interacting short crack growth in blocky alpha Zircaloy-4 (KC 4)
W. Wan, F.P.E. Dunne
International Journal of Plasticity https://doi.org/10.1016/j.ijplas.2020.102711
Theory and application of Weibull distributions to 1D peridynamics for brittle solids (KC 4)
L.D. Jones, L.J. Vandeperre, T.A. Haynes, M.R.Wenman
Computer Methods in Applied Mechanics and Engineering https://doi.org/10.1016/j.cma.2020.112903
Understanding the role of Fe, Cr and Ni in Zircaloy-2 with special focus on the role of Ni on hydrogen pickup (KC 3 & 4)
Y.R. Than, R.W. Grimes, B.D.C. Bell, M.R. Wenman
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2019.151956
2019
The effect of δ-hydride on the micromechanical deformation of a Zr alloy studied by in situ high angular resolution electron backscatter diffraction (KC 2 & 4)
S. Wang, S. Kalácska, X. Maeder, J. Michler, F. Giuliani, T.B. Britton
Scripta Materialia https://doi.org/10.1016/j.scriptamat.2019.08.006