The activated corrosion product assessments of fusion structural materials are essential to designing components and evaluating workers' radiation exposure. This paper first gives the R&D status of the high-temperature pressurized water corrosion study of reduced activation ferritic/martensitic steels and chromium–zirconium–copper (CuCrZr) alloys, which are the leading candidate materials of fusion reactor in-vessel components such as breeding blanket and divertor, which are utilized in high-temperature and high-pressure water, and the recent progress of corrosion test apparatus simulating the unique environment of a fusion reactor will also be presented.
This paper discusses the R&D status of high-temperature pressurized water corrosion studies on fusion reactor materials like reduced activation ferritic/martensitic steels and CuCrZr alloys. It also presents the recent progress in corrosion test apparatus simulating fusion reactor environments.
Present status of liquid metal research for a fusion reactor