2026 Brian D. Wirth: Materials Science Researcher – H-Index, Publications & Awards

Discipline name	D-Index	World Ranking	Current World Ranking	National Ranking	Current National Ranking	Publications	Citations
Materials Science	68	4864	4708	1289	1210	390	16302

Discipline name

D-Index

World Ranking

Current World Ranking

National Ranking

Current National Ranking

Publications

Citations

Materials Science

4864

4708

1289

1210

390

16302

Overview

Brian D. Wirth is affiliated with the University of Tennessee at Knoxville in the United States. Their research spans multiple areas within materials science and engineering, with a focus on nuclear materials and fusion technologies.

Their main fields of study include materials science and engineering, supported by extensive work in subfields such as materials chemistry, aerospace engineering, nuclear and high energy physics, mechanics of materials, and inorganic chemistry.

The topics most frequently addressed in their research are:

Fusion materials and technologies
Nuclear materials and properties
Nuclear reactor physics and engineering
Magnetic confinement fusion research
Metal and thin film mechanics
Radioactive element chemistry and processing
Ion-surface interactions and analysis

Brian D. Wirth has contributed extensively to the literature with recent papers including:

Perspectives on multiscale modelling and experiments to accelerate materials development for fusion (2021, Journal of Nuclear Materials)
Predicting structural material degradation in advanced nuclear reactors with ion irradiation (2021, Scientific Reports)
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing (2020, Journal of Nuclear Materials)
Revealing the synergistic effects of sequential and simultaneous dual beam irradiations in tungsten via in-situ TEM (2020, Journal of Nuclear Materials)
Theoretical Model of Helium Bubble Growth and Density in Plasma-Facing Metals (2020, Scientific Reports)

Collaborative work is a significant feature of their research, with frequent co-authors including Yang Li, Dimitrios Maroudas, Sophie Blondel, Dwaipayan Dasgupta, and A. Lasa.

Publication venues where Brian D. Wirth most often publishes include:

Journal of Nuclear Materials
Nuclear Fusion
Journal of Applied Physics
SSRN Electronic Journal
arXiv (Cornell University)

Best Publications

Recent Developments in Irradiation-Resistant Steels

G.R. Odette;M.J. Alinger;B.D. Wirth

1381
Citations
Multiscale modelling of plastic flow localization in irradiated materials

Tomas Diaz de la Rubia;Hussein M. Zbib;Tariq A. Khraishi;Brian D. Wirth

366
Citations
Primary damage formation in bcc iron

R.E. Stoller;G.R. Odette;B.D. Wirth

362
Citations
Hydrogen in zirconium alloys: A review

Arthur T. Motta;Laurent Capolungo;Long Qing Chen;Mahmut Nedim Cinbiz

335
Citations
Thermal stability of helium-vacancy clusters in iron

K. Morishita;R. Sugano;B.D. Wirth;T. Diaz de la Rubia

334
Citations
Tungsten surface evolution by helium bubble nucleation, growth and rupture

Faiza Sefta;Karl D. Hammond;Niklas Juslin;Brian D. Wirth;Brian D. Wirth

322
Citations
Interatomic potentials for simulation of He bubble formation in W

N. Juslin;B.D. Wirth

311
Citations
Comparative study of radiation damage accumulation in Cu and Fe

M.J. Caturla;N. Soneda;E. Alonso;B.D. Wirth

293
Citations
Irradiation hardening of pure tungsten exposed to neutron irradiation

Xunxiang Hu;Takaaki Koyanagi;Makoto Fukuda;N.A.P. Kiran Kumar

277
Citations
Mechanism of formation and growth of interstitial loops in ferritic materials.

Jaime Marian;Brian D. Wirth;J. Manuel Perlado

269
Citations
Atomistic Shock Hugoniot simulation of single-crystal copper

E. M. Bringa;J. U. Cazamias;Paul Erhart;J. Stölken

269
Citations
A review of TRISO fuel performance models

Jeffrey J. Powers;Brian D. Wirth

267
Citations
Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron

B.D Wirth;G.R Odette;D Maroudas;G.E Lucas

246
Citations
Precipitation in neutron-irradiated Fe-Cu and Fe-Cu-Mn model alloys : a comparison of APT and SANS data

M.K. Miller;B.D. Wirth;G.R. Odette

224
Citations
Energetics of formation and migration of self-interstitials and self-interstitial clusters in α-iron

B.D. Wirth;G.R. Odette;D. Maroudas;G.E. Lucas

212
Citations
In-situ transmission electron microscopy observations and molecular dynamics simulations of dislocation-defect interactions in ion-irradiated copper

J. S. Robach;I. M. Robertson;B. D. Wirth;A. Arsenlis

210
Citations
MD and KMC modeling of the growth and shrinkage mechanisms of helium–vacancy clusters in Fe

K. Morishita;R. Sugano;B.D. Wirth

208
Citations
A computational microscopy study of nanostructural evolution in irradiated pressure vessel steels

G.R. Odette;B.D. Wirth

191
Citations
How Does Radiation Damage Materials

Brian D. Wirth

184
Citations
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys

Gary S. Was;Janelle P. Wharry;Brian Frisbie;Brian D. Wirth

183
Citations