25th IAEA Fusion Energy Conference - IAEA CN-221

Neutron Irradiation Effects on Grain-Refined W and W-Alloys

17 Oct 2014, 08:30

4h

Green 8-9 (Hotel Park Inn Pribaltiyskaya)

Poster Poster 7

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 400-800C 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.