核融合中性子照射環境における材料工学入門

概要

論文の詳細を見る
The effect of radiation on structural materials is one of the critical considerations in the development of fusion reactors. Displacement damage by 14MeV neutrons usually measured by the unit of dpa causes microstructural changes in irradiated materials, which then modify their macroscopic properties. Austenitic steels have relatively large database on irradiation performance including hardening, elongation, fracture toughness, irradiation creep, corrosion, swelling and helium embrittlement. Reduced activation materials, such as low activation ferritic steels, SiC/SiC composites and vanadium alloys have advantage to future fusion reactors. Engineering database and fabrication technology as well as irradiation test database should be established to mature materials for fusion applications. The importance of multi-scale modeling of materials behavior under fusion environments is also pointed out.
社団法人プラズマ・核融合学会の論文
1998-11-25