Weicheng Zhong

R&D Staff Scientist

Contact

865.241.7293 | ZHONGW@ORNL.GOV

All Publications

Computational materials assessment of the D/Li-stripping neutron source as a prototypical facility for fusion materials testing

MX precipitate behavior in an irradiated advanced Fe-9Cr steel: Self-ion irradiation effects on phase stability

Hydrogen charging and desorption from microstructural viewpoint: A method for deconvoluting hydrogen desorption spectra and unveiling the hydrogen-microstructure interaction

Relative phase stability of L12 and DO22/DO23 structures in Al3Nb, Al3Zr and Al3V compounds

Deuterium Trapping Mechanisms in Reduced Activation Ferritic Martensitic Steels and Their Correlation with Mechanical Strengthening

Simultaneous exposure to neutron radiation and hydrogen environment: Effect on hydrogen retention

Simultaneous Exposure of Tungsten and Tungsten - Rhenium Alloy to Neutron Irradiation and Hydrogen Environment

Gas tungsten arc welding and post weld heat treatment effects on microstructure and mechanical property of castable nanostructured alloy steel

High-temperature nanoindentation creep studies on castable and sintered nanostructured low-activation ferritic-martensitic alloys

MX precipitate behavior in an irradiated advanced Fe-9Cr steel: Helium effects on phase stability

Computational Design of Improved Fast Reactor Cladding

Microstructure, stored energy, and stability of H/He-filled nanocavities in low temperature irradiated Inconel 718

MX precipitate behavior in an irradiated advanced Fe-9Cr steel: Helium sequestration and cavity swelling performance

Effect of microstructure and neutron irradiation defects on deuterium retention in SiC

Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides

The microstructure effects on irradiation response of ferritic – martensitic steels

Degradation of electrical resistivity of tungsten following shielded neutron irradiation

Sintered nanostructured alloys for advanced fusion energy applications

Multimodal Characterization of Stored Energy and Gas-Filled Cavities in FCC Alloys Irradiated with Spallation Neutrons and High-Energy Protons

Deciphering the multiple deformation mechanisms responsible for sustained work hardening in a FeCrCoNi medium entropy alloy

Irradiation-assisted cracking of SA508-304L weldments with 308L groove filler and 309L butter in hot water immersion constant rate extension tests

Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding

Creep behavior of an additively manufactured 9Cr steel in the as-built condition

Report summarizing demonstration of thermal conductivity measurement methods for coated zirconium cladding

Microstructure analysis of laser beam weldments performed on neutron-irradiated 304L steel containing 3 and 8 appm helium