2022 Fall Meeting

Presentation information

Oral presentation

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

[2H10-13] Fusion Material Engineering 1

Thu. Sep 8, 2022 2:45 PM - 3:50 PM Room H (E1 Bildg.3F No.33)

Chair:Makoto Kobayashi(NIFS)

3:00 PM - 3:15 PM

[2H11] Effect of dissolved oxygen concentration on surface of CuCrZr alloy in high temperature/pressurized water

*Naofumi Nakazato1, Ryota Sugiyama1, 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

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. The cooling water would be irradiated by neutrons and brought about the radiolysis of water. The radiolysis of water forms molecular (hydrogen, oxygen and etc.) and radical species which participate to the corrosion of the structural materials. Therefore, it is also important to accumulate the fundamental data of that of CuCrZr alloy considering the change in water chemistry conditions due to the radiolysis of water. The objective of this research is to evaluate the effect of dissolved oxygen concentration on CuCrZr alloy in high temperature/pressurized water.