2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[2P19-23] Advanced Fuels/Fundamental Properties

Thu. Sep 14, 2017 5:10 PM - 6:30 PM Room P (Seminar room 2 - Frontier Research in Applied Sciences Building)

Chair:Shuhei Miwa (JAEA)

5:40 PM - 5:55 PM

[2P21] High-Temperature oxidation behavior of advanced fuel cladding SiC under various oxygen partial pressures

*Souichirou Yamaguchi1, Aikebaier Yusufu1, Takuma Shirahama1, Yukihiro Murakami1, Masayoshi Uno1 (1. Research Institute of Nuclear Engineering, University of Fukui)

Keywords:Silicon Carbide, High-Temperature oxidation behavior, oxygen partial pressure, Thermodynamic calculations

SiC is gaining attention in nuclear fuel cladding applications as a promising fuel cladding. To understand its soundness, the high-temperature oxidation behavior of high-density bulk SiC was investigated in air and vacuum (10Pa) and the validity of the experimental results was confirmed by thermodynamic calculations.