[1L06-09] Plasma Engineering/Irradiation Behavior

[1L08] Influence of neutron irradiation on deuterium release from tungsten

*Yuji Hatano¹, Vladimir Kh. Alimov², Tatsuya Kuwabara³, Takeshi Toyama⁴, Alexander V. Spitsyn², Youji Someya⁵ (1. HRC, U. Toyama, 2. NRC “Kurchatov Institute", 3. Aichi Inst. Technol., 4. IMR, Tohoku U., 5. QST)

Keywords:Plasma-facing component, Tritium, Decontamination, Neutron irradiation, Tungsten

One of the possible tiritium removal methods from plasma-facing component (PFCs) is to heat PFCs to ~300 ℃ in a vacuum vessel after DT operation using decay heat. In this study, W samples were irradiated with neutrons in a fission reactor BR2, and release of deuterium (D) in a vacuum at 300 ℃ from the irradiated and non-irradiated W samples was examined after exposure to high flux D plasma at 300, 400 and 500 ℃. The majority of D retained in the non-irradiated samples was released by heating for 30 h. Far slower but clear release of D was observed for the neutron-irradiated samples. The possible D removal by heating for longer time (~1 month) will be simulated and reported.