Tungsten (W) is a primary candidate for plasma-facing components in fusion reactors but suffers from severe microstructural damage under helium (He) ion irradiation. Key irradiation parameters including incident ion energy, fluence, and radiation temperature determine the formation of He bubbles, dislocation loops, and surface blistering, ultimately leading to mechanical degradation including radiation hardening and ductile-to-brittle transition temperature (DBTT) shifts. To address these challenges, various strategies such as interface engineering and alloying have been developed to improve He radiation tolerance. Recent studies have improved understanding of the underlying mechanisms driving defect evolution and mechanical performance degradation, offering insights into the design of more resilient W-based materials for extreme environments.