2017 Fall Meeting

Presentation information

Oral presentation

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

[3M05-10] Advanced Material 2

Fri. Sep 15, 2017 2:45 PM - 4:25 PM Room M (N304 - N Block)

Chair:Tamaki Shibayama (Hokkaido Univ.)

3:00 PM - 3:15 PM

[3M06] R&D of advanced stainless steels for BWR fuel claddings (2)

(2)Material performance during severe accidents

*Tomohiko Ikegawa1, Ryo Ishibashi1, Kan Sakamoto2, Mutsumi Hirai2, Shinichiro Yamashita3 (1. Hitachi-GE, 2. NFD, 3. JAEA)

Keywords:Accident tolerant fuel, Fuel cladding, Severe accident, BWR, Core damage, Hydrogen generation

An accident tolerant fuel cladding made of a FeCrAl-ODS steel for BWR is being developed. As one topic of series of presentations, I will introduce a FeCrAl-ODS steel cladding performance during severe accidents, especially a timing of core damage and an amount of hydrogen generation compared with Zr alloy used for conventional BWRs.