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)

10:00 AM - 10:15 AM

[3L03] Corrosion Issues of Cu-alloy toward DEMO Divertor

(3)Corrosion behavior of CuCrZr alloy in hydrogen-dissolved high temperature high pressure water environment

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

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

The compatibility of Cu-alloy (CuCrZr) with high-temperature high-pressure water, and its corrosion behavior was evaluated. Static corrosion tests in hydrogen-dissolved water were conducted up to 500hr. Weight change of specimens was smaller than those in deaerated water. Specimen surface was sponge-like with crystals on surface.