Overview of the US-Japan Collaborative Investigation on Hydrogen Isotope Retention in Neutron-Irradiated and Ion-Damaged Tungsten.

摘要

Plasma-facing components (PFCs) will be exposed to 14 MeV neutrons from D-T fusion reactions, and tungsten, a candidate material for the divertor PFC in ITER, is expected to receive a neutron dose of 0.7 displacement per atom (dpa) by the end of operation in ITER. The effect of neutron-irradiation damage has been mainly simulated using high-energy ion bombardment at different linear plasma devices or ion-implantation experiments with different tungsten materials. A recent MIT report (written by members of the Divertor/Scrape-Off Layer subgroup of the International Tokamak Physics Activity) summarizes the observations from high-energy ion bombardment studies and illustrates the saturation trend in deuterium concentration due to damage from ion irradiation in tungsten and molybdenum above 1 dpa.