Brian D. Wirth

Oak Ridge National Laboratory — United States

Materials Science · Physical Sciences

64h-index15.3kcitations559works2.62yr avg
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Research Topics

Fusion materials and technologies(356), Nuclear Materials and Properties(316), Nuclear reactor physics and engineering(90), Ion-surface interactions and analysis(77), Magnetic confinement fusion research(55)

Publications554 total

Palladium corrosion of the SiC layer in TRISO particle fuels: A separate effects study to assess mechanisms for palladium attack
Progress in Nuclear Energy·2026
MHD-induced SOL filaments and divertor heat flux striations in NSTX
Plasma Physics and Controlled Fusion·2026
Spherical tokamak physics research in preparation for the operation of NSTX-U
Nuclear Fusion·2026Open Access
Surface morphological response of plasma-facing tungsten: Effects of surface crystallographic orientation and prediction of fuzz onset
Journal of Nuclear Materials·2026
First-principles study of formation, diffusion, and recombination of defects in YBa <sub>2</sub> Cu <sub>3</sub> O <sub>7</sub>
Superconductor Science and Technology·2025
Multiphysics Fuel Performance Modeling of TRISO-Bearing Fuel in Advanced Reactor Environments
Nuclear Science and Engineering·2025Open Access
Interpreting experimental measurements of helium bubbles using stochastic cluster dynamics models of heterogeneous nucleation and growth in irradiated ferritic alloys
Journal of Nuclear Materials·2025Open Access
An Initial Microstructurally Informed Model of High Burnup Structure Formation in UO <sub>2</sub> Fuel
Nuclear Science and Engineering·2025· 1 cited
Atomistic simulation of xenon bubble re-solution at dislocations versus in bulk UO2 due to thermal spike
Journal of Nuclear Materials·2025
Simulations of grain growth in tungsten armor materials under ARC plasma edge operation conditions using an integrated plasma-edge/materials model
arXiv (Cornell University)·2025Open Access
Observation of stationary filaments with resonant magnetic perturbations in NSTX
Nuclear Fusion·2025· 3 citedOpen Access
Mechanistic Multiscale Uncertainty Propagation in Support of Accelerated Fuel Qualification
Nuclear Technology·2025· 5 cited
Computer-Assisted Proofs for Geometric Optimization: From Crystallization to Carbon Nanotubes
ArXiv.org·2025Open Access
A thermodynamic theory of coupling between point-defect diffusion and dislocation plasticity
Journal of Applied Physics·2025· 2 citedOpen Access
Investigation of He retention in W through combined He characterization methods and cluster dynamics model
Nuclear Science and Techniques·2025· 2 cited
Atomistically-informed cluster dynamics modeling of concurrent interstitial and vacancy a-loop evolution in irradiated alpha-zirconium
Acta Materialia·2025· 1 citedOpen Access
Influence of temperature, initial grain-boundary bubble density and grain structure on fission gas behaviour in UO2: a 3D hybrid multiscale study
SSRN Electronic Journal·2025Open Access
Simulations of grain growth in tungsten armor materials under ARC plasma edge operation conditions using an integrated plasma-edge/materials model
SSRN Electronic Journal·2025Open Access
Palladium Corrosion of the Sic Layer in Triso Particle Fuels: A Separate Effects Study to Assess Mechanisms for Palladium Attack
SSRN Electronic Journal·2025Open Access
Effects of Surface Crystallographic Orientation on the Surface Morphological Response of Plasma-Facing Tungsten
SSRN Electronic Journal·2025Open Access
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Frequent Co-authors

G.R. Odette(7), Jaime Marian(7), T. Dı́az de la Rubia(6), G.R. Odette(5), Karl D. Hammond(5), Xunxiang Hu(5), Dimitrios Maroudas(5), M.J. Caturla(4), N. Juslin(4), J.M. Perlado(3), G.E. Lucas(3), Gary S. Was(3), Dane Morgan(3), Mark R. Gilbert(3), Richard J. Kurtz(3), Laurent Capolungo(2), Kazunori Morishita(2), R. Sugano(2), Faiza Sefta(2), Takaaki Koyanagi(2)