日本原子力学会 2014年春の年会

Presentation information

一般セッション

III. 核分裂工学 » 304-1 伝熱・流動(エネルギー変換・輸送・貯蔵を含む)

[M31-36] 福島事故セッション2

Thu. Mar 27, 2014 2:30 PM - 4:05 PM M (1号館 12L)

座長:古谷正裕(電中研)

[M35] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(20) Oxidation model improvement in SAMPSON considering steam conservation and cladding rupture

Maolong Liu1, Yuki Ishiwatari2, Nejdet Erkan1, Koji Okamoto1 (1.The University of Tokyo, 2.Hitachi GE)

Keywords:Fukushima accident, Oxidation reaction, Creep rupture

Oxidation reaction of these metals with high-temperature steam would have significant impacts on the melting and subsequent core relocation. During the core heat-up, the small leakage flow of steam caused by failure of the reactor coolant system pressure boundary determines the availability and the distribution of steam in the core, which could limit the total amount of oxidation energy.