midas kc3 publications
2024
Modelling amorphization and dissolution of Zr(Fe,Cr)2 secondary phase precipitates in Zircaloys (KC 1 & 3)
J. Robson
Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2024.15535
2023
Discrete dislocation dynamics simulations of -type prismatic loops in zirconium (KC 2)
D. Hortelano Roig, R. Kumar, D. Balint, E. Tarleton
International Journal of Plasticity, https://doi.org/10.1016/j.ijplas.2023.10380
Solute Concentrations in the Matrix of Zirconium Alloys Studied by Atom Probe Tomography (KC1 & 3)
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
Understanding the Mechanistic Role of Lithium in Accelerated Corrosion of Zirconium Alloys Using Advanced Characterization and Atomistic Simulation (KC 3)
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
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
Diffusion in undoped and Cr-doped amorphous UO2 (KC 3)
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
Untangling competition between epitaxial strain and growth stress through examination of variations in local oxidation (KC 3)
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
High temperature zirconium alloys for fusion energy (KC 3)
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
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
Untangling competition between epitaxial strain and growth stress through examination of variations in local oxidation (KC 3)
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
The accommodation of lithium in bulk ZrO2 (KC 3)
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
Diffusion in doped and undoped amorphous zirconia (KC 3)
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
Oxide growth and oxygen transport in proton irradiated Zircaloy-4 oxide layers (KC 3)
C. Jones, M. Gass, M. Preuss, K.L.Moore
Corrosion Science https://doi.org/10.1016/j.corsci.2021.109655
Photon Irradiation Effects on Oxide Surface Electrochemistry and Oxide Microstructure of Zircaloy 4 in High-Temperature Water (KC 3)
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 Importance of Substrate Grain Orientation on Local Oxide Texture and Corrosion Performance in α-Zr Alloys (KC 3)
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
A Review of Early Findings within the Collaborative Research Programme MUZIC—“Mechanistic Understanding of Zirconium Corrosion” (KC 3)
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 (KC 3)
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
Effect of sample thinning on strains and lattice rotations measured from Transmission Kikuchi diffraction in the SEM (KC 2 & 3)
P.S. Karamche, N. Saravanan, J.C.Haley, A.J.Wilkinson, S. Lozano-Perez
Ultramicroscopy https://doi.org/10.1016/j.ultramic.2021.113267
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
2020
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
Cu and Sb in tetragonal ZrO2 on fuel cladding (KC 3)
Y. R. Thana, M. R. Wenman, R. W. Grimes
Journal of Applied Physics https://doi.org/10.1063/5.0021174
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
Assessment of annealing parameter approximations in zirconium alloys (KC 3)
J.D. Robson
Journal of Nuclear Materials https://doi.org/10.1016/j.jnucmat.2019.151814