2020 Annual Meeting

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Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[2M01-03] Corrosion

Tue. Mar 17, 2020 10:00 AM - 10:50 AM Room M (Lecture Bildg. S 3F S-31)

Chair:Tatsuya Hinoki(Kyoto Univ.)

10:30 AM - 10:45 AM

[2M03] Corrosion of Ni-based alloy with molten fluoride salt under strong oxidizing condition

*Koji Ogasawara1, Yuma Sekiguchi1, Takayuki Terai1 (1. Univ. of Tokyo)

Keywords:Molten salt reactor, Corrosion, FLiNaK, Ni-based alloy

As one of the corrosion research concerning Molten Salt Reactors, it was evaluated how oxidizing materials such as Li2O, O2, and Te coexisting with molten FLiNaK salt affect the corrosion of Ni-based alloys such as Hastelloy and Inconel. Hastelloy showed better corrosion resistance than Inconel in the strong oxidizing condition as well. Also, the corrosion protection of Zr as a sacrificial metal was confirmed.