2021 Annual Meeting

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Oral presentation

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

[3L10-15] Tritium Engineering

Fri. Mar 19, 2021 2:45 PM - 4:30 PM Room L (Zoom room 12)

Chair: Hirofumi Nakamura (QST)

3:45 PM - 4:00 PM

[3L14] Computer simulation of tritium recovery from neutron-irradiated tungsten

*Yuji Hatano1, Azusa Matsumoto1 (1. Univ. of Toyama)

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

Irradiation of 14 MeV neutrons of tungsten induces lattice defects acting as trapping site against hydrogen isotopes. Hence, significant increase in tritium retention in tungsten is expected after neutron irradiation. Recoverty of tritium from neutron-irradiated tungsten is important from the view points of tritium economy and safe disposal of spent plasma-facing components. In this study, efficiency of tritium recovery of neutron-irradiated tungsten by bake out procedure was evaluated from the values of trap density and trapping energy reported in literature by using diffusion analysis code TMAP.