2023 Annual Meeting
Mar 13 - Mar 15, 2023Tokyo University Komaba Campus
2023 Annual Meeting
Mar 13 - Mar 15, 2023Tokyo University Komaba Campus
[1A07]High Accurate Evaluation of Deuterium and Helium Behavior in Tungsten by STEM-EELS
*Kohei Sano1, Tomoya Sawae1, Mitsutaka Haruta2, Hiroki Kurata2, Mitsutaka Miyamoto1(1. Shimane Univ., 2. Kyoto Univ.)
Keywords:
Nuclear fusion reactor,Gas retention characteristics,Helium bubble,deuterium,tungsten
It has been reported that the retention of deuterium (D) increases significantly in W pre-irradiated with helium (He), which is a major contributor to defect formation, and that He has a significant effect on the D retention behavior. However, although various studies have been conducted on the mechanism, no conclusive findings have yet been obtained. In this experiment, thin film samples were prepared after He pre-irradiation and D irradiation, and the presence and trap positions of D and He in W were quantitatively evaluated using a STEM-EELS at Kyoto University. The results suggest that most of D in W is trapped in He bubbles. In the presentation, the dependence on He pre-irradiation dose and sample temperature will also be discussed.