Cs Adsorption Behavior Evaluation on the Surface of Nuclear Reactor Structure Materials under High Temperature High Pressure Steam

Takehiro Sumita

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 405-3 Decommissioning Technology of Nuclear Facilities

[2H18-22] Influence of materials in Severe accident

Tue. Mar 28, 2017 5:10 PM - 6:30 PM Room H (16-303 Building No.16)

Chair: Hiroshi Masaki (TOSHIBA)

5:55 PM - 6:10 PM

[2H21] Cs Adsorption Behavior Evaluation on the Surface of Nuclear Reactor Structure Materials under High Temperature High Pressure Steam

*Takehiro Sumita¹, Kazuo Yonekawa², Yoshihiro Sekio², Isamu Sato¹, Yoshinao Kobayashi¹, Masahiko Osaka², Koji Maeda², Naoaki Akasaka² (1. Tokyo Institute of Technology, 2. JAEA)

Keywords:SA, High Temperature High Pressure Steam, Fission product, Adsorption, Cs

福島第一原子力発電所におけるシビアアクシデント時の炉心状況(高温・高圧水蒸気環境)を模擬して、構造材であるステンレス鋼へCsIを作用させてその吸着挙動を評価した。