2017 Annual Meeting

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Oral presentation

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

[2J15-17] Fuel Cladding Tube 3

Tue. Mar 28, 2017 5:40 PM - 6:30 PM Room J (16-305 Building No.16)

Chair: Terumitsu Miura (INSS)

5:40 PM - 5:55 PM

[2J15] Development of Corrosion Resistant Coating Technology to Silicon Carbide Fuel Materials

*Ryo Ishibashi1, Shinya Okamoto1, Kazushige Ishida3, Takao Kondo2, Katsumasa Miyazaki1 (1. Center for Technology Innovation - Materials, Research & Development Group, Hitachi, Ltd., 2. Hitachi-GE Nuclear Energy, Ltd, 3. Center for Technology Innovation - Energy, Research & Development Group, Hitachi, Ltd.)

Keywords:Silicon carbide, Coating, Adhesion, Corrosion resistance, Fuel materials

For the purpose of improving corrosion resistance of silicon carbide (SiC) in a simulated BWR-NWC environment, corrosion resistant coatings to SiC substrate were examined. Chromium, titanium and zirconium alloy coatings processed by physical vapor deposit and subsequently heat treatment were evaluated in terms of adhesion to SiC during coating process and corrosion resistance in high temperature water.