Yunxiang Long

Wuhan University of Technology — China

Materials Science · Physical Sciences

13h-index368citations30works2.82yr avg
OpenAlex↗ORCID↗Google Scholar↗Lab page↗

Accepting Students?

No reports yet. Know if this professor is taking students?

Research Topics

Fusion materials and technologies(24), Nuclear Materials and Properties(19), Hydrogen embrittlement and corrosion behaviors in metals(8), Ion-surface interactions and analysis(5), High voltage insulation and dielectric phenomena(4)

Publications30 total

Significant amplification of irradiation dose effects by hydrogen-helium and the mechanism based on rate theory
Journal of Nuclear Materials·2025
Temperature effect on cavity evolution by triple-beam irradiation
Journal of Nuclear Materials·2025· 1 cited
Effect of irradiation with varying H/He ratio on defect clusters and hardening in CLAM steel
Journal of Alloys and Compounds·2025· 1 cited
Dislocation loops and hardening of silicon ion irradiated W and W-3Re alloy at 400 °C and 550 °C
Journal of Nuclear Materials·2024· 6 cited
Superior radiation resistance of ODS-RAFM steels revealed by Positron annihilation spectroscopy study
Journal of Materials Research and Technology·2024· 10 citedOpen Access
The effect of hydrogen-helium synergism on dislocation loops in RAFM steel at different temperatures by dual-beam ion irradiation
Journal of Nuclear Materials·2024· 4 cited
Superior Radiation Resistance of Rafm-Ods Steels Revealed by Positron Annihilation Spectroscopy Study
SSRN Electronic Journal·2024Open Access
Behavior of Helium and Hydrogen in Rafm Series Steels During the Early Stage of Vacancy Defect Evolution
SSRN Electronic Journal·2024Open Access
Microstructure evolution and void swelling of ODS ferritic/martensitic steel under high damage irradiation
Materials Characterization·2023· 21 cited
Deterioration of irradiation resistance of ODS-F/M steel under high concentration of helium
Journal of Nuclear Materials·2023· 24 cited
Microstructure Evolution and Void Swelling of Ods Ferritic/Martensitic Steel Under High Damage Irradiation
SSRN Electronic Journal·2023· 7 citedOpen Access
Ion Irradiation Defects and Hardening in FeCrAl Alloy
Metals·2022· 7 citedOpen Access
Effects of different silicon content on irradiation defects and hardening in 9Cr ferritic/martensitic steel
Journal of Nuclear Materials·2022· 20 cited
Establishment of multi-beam irradiation facility at Wuhan University
Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment·2022· 32 cited
Effect of helium and its synergism with displacement damage on microstructure of CLAM steel investigated by single, sequential and simultaneous Fe and He ion irradiations
Journal of Nuclear Materials·2022· 22 cited
Microstructure Evolution and Void Swelling of Ods Ferritic/Martensitic Steel Under High Damage Irradiation at 550 °C
SSRN Electronic Journal·2022Open Access
Effect of niobium content on irradiation microstructure and hardening in FeCrAl-based alloys
Journal of Material Science and Technology·2021· 53 cited
Rate theory and experimental study of the irradiation induced defects in molybdenum alloy
Journal of Alloys and Compounds·2021· 15 cited
Electron Swarms Parameters in CF<sub>3</sub>SO<sub>2</sub>F as an Alternative Gas to SF<sub>6</sub>
Industrial & Engineering Chemistry Research·2020· 24 cited
Measurement of Ionization and Attachment Coefficients in C<sub>4</sub>F<sub>7</sub>N/CO<sub>2</sub> Gas Mixture as Substitute Gas to SF<sub>6</sub>
IEEE Access·2020· 17 citedOpen Access
page 1 of 2Next →

Frequent Co-authors

Liping Guo(28), Hongtai Luo(15), Yiheng Chen(13), Ziyang Xie(13), Wenbin Lin(12), Zhenyu Shen(10), Yaxia Wei(10), Cheng Chen(9), Junjie Cao(9), Weiping Zhang(8), Fang Li(7), Zepeng Yin(7), Rui Yan(7), Xiong Zhou(6), Yiheng Chen(6), Shuoxue Jin(5), Hui Wang(4), Shaobo Mo(4), Wenjun Zhou(4), Zhangjian Zhou(4)