2021 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[3L01-04] Chemical Compatibility of Materials 1

Fri. Mar 19, 2021 9:30 AM - 10:35 AM Room L (Zoom room 12)

Chair: Teruya Tanaka (NIFS)

9:30 AM - 9:45 AM

[3L01] Corrosion Issues of Cu-alloy toward DEMO Divertor

(1)An Overview of Domestic and International Research Activities and the Status of Instrumentation at QST

*Motoki Nakajima1, Yen-jui Huang1, Naofumi Nakazato2, Taisei Nemoto2, Yu Seiriki2, Takashi Nozawa1, Hirotatsu Kishimoto2 (1. QST, 2. Muroran IT)

Keywords:Diverter, Corrosion, Cu-alloy, High temperature pressurized water

In ITER and JA-DEMO diverters, Cu-alloy is planned to be used as the coolant tube due to its excellent thermal conductivity. Although both diverters use high-temperature pressurized water as a coolant, understanding the compatibility of Cu-alloy with coolant is not yet sufficient. This series of presentations summarize the corrosion issues of Cu-alloy that are being addressed in collaboration with domestic and foreign organizations towards DEMO, and in this presentation, an overview of the joint research being conducted in Japan, the corrosion issues to be dealt with in the broader approach activities, and an overview of the corrosion test equipment being developed in QST will be introduced.