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)

9:45 AM - 10:00 AM

[3L02] Corrosion Issues of Cu-alloy toward DEMO Divertor

(2)Compatibility Evaluation of CuCrZr alloy in Deaerated High Temperature Pressurized Water

*Naofumi Nakazato1, Taisei Nemoto1, Yu Seiriki1, Motoki Nakajima2, Yen-Jui Huang2, Takashi Nozawa2, Hirotatsu Kishimoto1 (1. Muroran IT, 2. QST)

Keywords:Divertor, CuCrZr alloy, Corrosion behavior, High temperature pressurized water

Muroran Institute of Technology is progressing a joint research for high temperature water corrosion of fusion reactor structural materials with the National Institutes for Quantum and Radiological Science and Technology. The CuCrZr alloy is one of the candidate structural materials for the divertor system. In order to ensure the soundness of divertor cooling system, it is necessary to find out a reasonable water chemistry condition. In the divertor, since the high temperature water corrosion property of CuCrZr ally is considered to affect by the neutron irradiation, it is also important to accumulate the fundamental data of that of CuCrZr alloy. The objective of this research is to evaluate the corrosion behavior of CuCrZr alloy in the deaerated high temperature pressurized water.