Brian D Wirth
Brian D Wirth
Governor's Chair Professor of Computational Nuclear Engineering, University of Tennessee
Zweryfikowany adres z utk.edu
Cytowane przez
Cytowane przez
Recent developments in irradiation-resistant steels
GR Odette, MJ Alinger, BD Wirth
Annu. Rev. Mater. Res. 38 (1), 471-503, 2008
Primary damage formation in bcc iron
RE Stoller, GR Odette, BD Wirth
Journal of Nuclear Materials 251, 49-60, 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
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
Tungsten surface evolution by helium bubble nucleation, growth and rupture
F Sefta, KD Hammond, N Juslin, BD Wirth
Nuclear Fusion 53 (7), 073015, 2013
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
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
Interatomic potentials for simulation of He bubble formation in W
N Juslin, BD Wirth
Journal of nuclear materials 432 (1-3), 61-66, 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
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
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
A review of TRISO fuel performance models
JJ Powers, BD Wirth
Journal of Nuclear Materials 405 (1), 74-82, 2010
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
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
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
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
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
A computational microscopy study of nanostructural evolution in irradiated pressure vessel steels
GR Odette, BD Wirth
Journal of Nuclear Materials 251, 157-171, 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
Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling
M Li, MA Kirk, PM Baldo, D Xu, BD Wirth
Philosophical Magazine 92 (16), 2048-2078, 2012
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