Dahuan Zhu

机构：Chinese Academy of Sciences, China General Nuclear Power Corporation (China), Institute of Plasma Physics, Key Laboratory of Nuclear Radiation and Nuclear Energy Technology · ORCID：0000-0001-6655-1372

发表论文 116 篇 · 总被引 947 次 · h-index 17

代表论文

• Microstructure evolution and hardening of helium ion irradiated tungsten (2025 · Vacuum · 被引 11)
• Experimental research on the deeply detached X-point radiator regime on EAST (2025 · Nuclear Fusion · 被引 5)
• Characterization of in situ damage to tungsten PFCs induced by transient heat flux during plasma disruption in EAST (2025 · Nuclear Fusion · 被引 5)
• Mechanism analysis of microstructural evolution induced by Y2O3 particles during the rolling process of W-Y2O3 composite (2025 · International Journal of Refractory Metals and Hard Materials · 被引 4)
• Investigation of the high-temperature tensile properties and helium ion irradiation resistance of W-La2O3 composites prepared by hot rolling (2025 · Fusion Engineering and Design · 被引 4)
• Enhanced thermal stability and irradiation resistance of ODS-W/CuCrZr joints by interlayer employ and interface improvement (2025 · Journal of Nuclear Materials · 被引 4)