2019 Fall Meeting

Presentation information

Oral presentation

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

[3H07-09] Severe Acident

Fri. Sep 13, 2019 11:10 AM - 12:00 PM Room H (Common Education Bildg. 2F B21)

Chair:Yoshinori Hashimoto(CRIEPI)

11:40 AM - 11:55 AM

[3H09] Study on high temperature oxidation behavior of cladding in air/steam mixture

*Yoshiyuki Nemoto1, Yoshiyuki Kaji1 (1. JAEA)

Keywords:Spent Fuel Pool, High temperature oxidation, Fuel cladding

Fuel cladding will be exposed to the air/steam mixture during lost of coolant or loss of coolability accident in spent fuel pool, and oxidized in high temperature. It was known that oxidation rate of Zr alloy cladding is higher in air than in steam, meanwhile the authors revealed that the oxidation rate in air/steam mixture is higher than which in dry air in some experimental conditions. Detail investigation results on this matter using zircaloy-4 cladding samples will be presented.