Radiation damage in tungsten under high-energy He-ion irradiation

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Authors: Yinghang Liu, Tanner McElroy, Chang Xia, Adil Wazeer, Maxwell Jacobson, Yexiang Xue, Guang Lin, Tim Graening, Xiao-Ying Yu, Haiyan Wang, Xinghang Zhang
Cited by: 1
References: 152

Abstract

Tungsten (W) is a primary candidate for plasma-facing components (PFCs) in fusion reactors and hybrid fission-fusion reactors. However, W suffers from severe microstructural damage under Helium (He) ion irradiation in operation conditions. Key irradiation parameters, including incident ion energy, fluence, and irradiation temperature, are known to determine the formation of He bubbles and dislocation loops, which ultimately lead to the degradation of mechanical properties, such as radiation hardening and ductile-to-brittle transition temperature (DBTT) shifts. Various strategies, for instance, interface engineering and alloying, have been developed to enhance He irradiation tolerance in W to address these challenges. Studies in the recent two decades have enhanced the understanding of the underlying mechanisms that drive defect evolution and mechanical performance degradation, thereby offering more insights into the design of more resilient W-based materials for extreme environments. Tungsten is a primary candidate for plasma-facing components in fusion reactors and hybrid fission-fusion reactors. This Review discusses microstructure damage in tungsten under irradiation from high-energy helium ions.

Fields of Study & Subjects

Fusion materials and technologies Nuclear materials and radiation effects Ion-surface interactions and analysis

Publication details

Journal / source
Communications Materials
Publisher
Springer Science and Business Media LLC
Volume
7
Issue
1
Publication date
26 May 2026
Language
EN