2020 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[1E01-07] Accident Tolerant Fuel

Wed. Sep 16, 2020 10:00 AM - 12:00 PM Room E (Zoom room 5)

Chair:Kazuo Kakiuchi(JAEA)

10:00 AM - 10:15 AM

[1E01] R&D for introducing silicon carbide materials to safety improvement of BWR's core

(7)Oxidation kinetics of SiC at 1400-1600oC under different steam flow rate

*Hai V. Pham1, Yuji Nagae1, Masaki Kurata1, Ryou Ishibashi2 (1. JAEA, 2. HGNE)

Keywords:SiC, steam oxidation, laser heating

Since the severe accident at Fukushima Daiichi nuclear power plant, development of accident tolerant fuel claddings such SiC has been intensively discussed. However, application of SiC as fuel claddings has raised some concerns over its performance under severe accident conditions in steam. In this study, investigation of steam oxidation for SiC at 1400-1600oC under 0.1 and 3 g/min steam flow rate was performed using newly developed laser heating facility. Results of the investigation showed that the SiC experienced a mass gain behavior under 0.1 g/min steam flow rate. Whereas, it suffered a mass loss under 3 g/min steam flow rate. Based on the mass change data obtained in the investigation, reaction rate constants and activation energy of the process were calculated and reported.