Speaker
Mr
Akira Hasegawa
(Japan)
Description
Microstructural data of neutron irradiated W such as size and number density of voids and precipitates obtained by W up to 1.5dpa irradiation in the temperature range of 400-800C were compiled quantitatively. Nucleation and growth process of these defects were clarified and a qualitative prediction of the damage structure development and hardening of W in fusion reactor environments were made taking into account the solid transmutation effects for the first time. Irradiation behavior of grain-refined W-alloys, produced by K- or La-doping, was also examined. Expected radiation resistant W-alloys, by combined Re addition and the grain refining process, were fabricated and characterization of unirradiated state were performed.
| Country or International Organisation | Japan |
|---|---|
| Paper Number | MPT/1-4 |
Primary author
Mr
Akira Hasegawa
(Japan)
Co-authors
Dr
Kiyohiro Yabuuchi
(Tohoku.University)
Mr
Makoto Fukuda
(Tohoku University)
Dr
Shuhei Nogami
(Tohoku University)
Dr
Takashi Tanno
(Japan Atomic Energy Agency)
Prof.
Takeo Muroga
(National Institute for Fusion Science)
Dr
Teruya Tanaka
(National Institute for Fusion Science)
