Recent developments in irradiation-resistant steels GR Odette, MJ Alinger, BD Wirth Annu. Rev. Mater. Res. 38 (1), 471-503, 2008 | 1343 | 2008 |
Primary damage formation in bcc iron RE Stoller, GR Odette, BD Wirth Journal of Nuclear Materials 251, 49-60, 1997 | 370 | 1997 |
Multiscale modelling of plastic flow localization in irradiated materials T Diaz de la Rubia, HM Zbib, TA Khraishi, BD Wirth, M Victoria, ... Nature 406 (6798), 871-874, 2000 | 363 | 2000 |
Thermal stability of helium–vacancy clusters in iron K Morishita, R Sugano, BD Wirth, TD De La Rubia Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2003 | 327 | 2003 |
Hydrogen in zirconium alloys: A review AT Motta, L Capolungo, LQ Chen, MN Cinbiz, MR Daymond, DA Koss, ... Journal of Nuclear Materials 518, 440-460, 2019 | 314 | 2019 |
Tungsten surface evolution by helium bubble nucleation, growth and rupture F Sefta, KD Hammond, N Juslin, BD Wirth Nuclear Fusion 53 (7), 073015, 2013 | 298 | 2013 |
Comparative study of radiation damage accumulation in Cu and Fe MJ Caturla, N Soneda, E Alonso, BD Wirth, TD De La Rubia, JM Perlado Journal of nuclear materials 276 (1-3), 13-21, 2000 | 287 | 2000 |
Interatomic potentials for simulation of He bubble formation in W N Juslin, BD Wirth Journal of nuclear materials 432 (1-3), 61-66, 2013 | 286 | 2013 |
Atomistic shock Hugoniot simulation of single-crystal copper EM Bringa, JU Cazamias, P Erhart, J Stölken, N Tanushev, BD Wirth, ... Journal of Applied Physics 96 (7), 3793-3799, 2004 | 263 | 2004 |
Mechanism of formation and growth of< 100> interstitial loops in ferritic materials J Marian, BD Wirth, JM Perlado Physical review letters 88 (25), 255507, 2002 | 257 | 2002 |
A review of TRISO fuel performance models JJ Powers, BD Wirth Journal of Nuclear Materials 405 (1), 74-82, 2010 | 244 | 2010 |
Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron BD Wirth, GR Odette, D Maroudas, GE Lucas Journal of nuclear materials 276 (1-3), 33-40, 2000 | 233 | 2000 |
Irradiation hardening of pure tungsten exposed to neutron irradiation X Hu, T Koyanagi, M Fukuda, NAPK Kumar, LL Snead, BD Wirth, Y Katoh Journal of Nuclear Materials 480, 235-243, 2016 | 230 | 2016 |
Precipitation in neutron-irradiated Fe–Cu and Fe–Cu–Mn model alloys: a comparison of APT and SANS data MK Miller, BD Wirth, GR Odette Materials Science and Engineering: A 353 (1-2), 133-139, 2003 | 218 | 2003 |
In-situ transmission electron microscopy observations and molecular dynamics simulations of dislocation-defect interactions in ion-irradiated copper JS Robach, IM Robertson, BD Wirth, A Arsenlis Philosophical Magazine 83 (8), 955-967, 2003 | 208 | 2003 |
Energetics of formation and migration of self-interstitials and self-interstitial clusters in α-iron BD Wirth, GR Odette, D Maroudas, GE Lucas Journal of nuclear materials 244 (3), 185-194, 1997 | 201 | 1997 |
MD and KMC modeling of the growth and shrinkage mechanisms of helium–vacancy clusters in Fe K Morishita, R Sugano, BD Wirth Journal of nuclear materials 323 (2-3), 243-250, 2003 | 199 | 2003 |
A computational microscopy study of nanostructural evolution in irradiated pressure vessel steels GR Odette, BD Wirth Journal of Nuclear Materials 251, 157-171, 1997 | 190 | 1997 |
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys GS Was, JP Wharry, B Frisbie, BD Wirth, D Morgan, JD Tucker, TR Allen Journal of Nuclear Materials 411 (1-3), 41-50, 2011 | 182 | 2011 |
Edge dislocation mobilities in bcc Fe obtained by molecular dynamics S Queyreau, J Marian, MR Gilbert, BD Wirth Physical Review B—Condensed Matter and Materials Physics 84 (6), 064106, 2011 | 155 | 2011 |