Presentation Information
[2I02]Study of Irradiation Hardening of Cavity in He Irradiated Pure Tungsten by In-situ TEM Observation during Deformation
*Kotaro Sato1, Kouichi Tougou1, Ken-ichi Fukumoto1 (1. Univ. of Fukui)
Keywords:
Tungsten,Ion irradiation,Irradiation hardening,TEM observation,Tensile test,Divertor
To investigation the mechanisms of irradiation hardening in tungsten (W), a candidate material for fusion reactor divertors, in-situ transmission electron microscope (TEM) observation under tensile testing was performed at room temperature on He-ion irradiated pure tungsten. Based on the line tensile model, just before a dislocation cut through a cavity, the obstacle strength α was evaluated from the bow-out angle of the dislocation at the cavity position. In the result, the obstacle strength α was 0.59 in a cavity size of 4.6 nm. Together with the results of previous study, it was found that the obstacle strength α tends to slightly increase as the cavity size increases.