2018 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[1D05-08] Corrosion

Mon. Mar 26, 2018 11:00 AM - 12:00 PM Room D (R1-212 -R1 Building)

Chair: Yoshiyuki Kaji (JAEA)

11:30 AM - 11:45 AM

[1D07] Corrosion behavior of Ni-based alloy in molten FLiNaK salt as a fundamental research on Molten Salt Reactors

*Koji Ogasawara1, Yuma Sekiguchi1, Takayuki Terai1, Hiroshi Kawamura2, Kunihiko Tsuchiya3, Takashi Watanabe4 (1. The Univ. of Tokyo, 2. Chiyoda Technol, 3. JAEA, 4. NIFS)

Keywords:Molten Salt Reactor, Ni-based alloy, Corrosion, FLiNaK, Reactor material

As a fundamental experiment for Molten Salt Reactors, Ni-based alloys(NCF 600) considered as reactor structural material were corroded with molten FLiNaK salt. After the experiment was done at 650℃, metals were observed with SEM/EDX. Overall, Cr and Fe were dissolved, and some cavities were seen near the surfaces.