Tritium dispersion in the Lithium-lead blanket loop

Fumito Okino

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[1H11-14] Hydrogen Isotope Behavior

Wed. Sep 7, 2022 4:10 PM - 5:15 PM Room H (E1 Bildg.3F No.33)

Chair:Takumi Chikada(Shizuoka Univ.)

4:40 PM - 4:55 PM

[1H13] Tritium dispersion in the Lithium-lead blanket loop

*Fumito Okino¹, Yukinori Hamaji ², Teruya Tanaka², Jyuro Yagi¹ (1. Institute of Advanced Energy, Kyoto University, 2. National Institute for Fusion Science)

Keywords:Lithium-lead, tritium, blanket, dispersion

Dispersion behavior of tritium in a lithium-lead blanket loop was verified by using the liquid metal test loop (Oroshhi-2) at National Institute for Fusion Science. The dispersion coefficient of tritium in a flowing lithium-lead was approximately 10^(-2)~10^(-3) m^2s^-1, six orders of mgnitudes faster than that of in a static conditon.