抄録
Neutron-irradiated tungsten (W) samples were exposed to helium (He)–seeded deuterium (D) plasmas using a linear plasma device called Tritium Plasma Experiment in order to investigate the synergetic effects of neutron and He irradiations on D retention in W. Exposure to nonseeded D plasma was also performed for neutron-irradiated and nonirradiated W samples for comparison. Deuterium retention in neutron-irradiated W after D plasma exposure was two to three times larger than that in W without neutron irradiation. Nevertheless, He seeding in D plasma resulted in a drastic reduction in D retention. The cross-sectional observation by transmission microscopy showed formation of He bubble layers with a thickness of 10 to 20 nm. There is a possibility that alpha particles in fusion plasma reduce tritium retention in neutron-irradiated plasma-facing components with W layers.
| 本文言語 | 英語 |
|---|---|
| ページ（範囲） | 76-79 |
| ページ数 | 4 |
| ジャーナル | Fusion Science and Technology |
| 巻 | 77 |
| 号 | 1 |
| DOI | |
| 出版ステータス | 出版済み - 2021 |
ASJC Scopus 主題領域
- 土木構造工学
- 核物理学および高エネルギー物理学
- 原子力エネルギーおよび原子力工学
- 材料科学一般
- 機械工学