2020 Annual Meeting

Presentation information

Oral presentation

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

[2L01-08] Tritium Release Behaviors, Production, Measurement

Tue. Mar 17, 2020 10:00 AM - 12:10 PM Room L (Lecture Bildg. S 2F S-22)

Chair:Teppei Otsuka(Kindai Univ.)

10:15 AM - 10:30 AM

[2L02] Tritium release from tungsten with radiation-induced defects

*Hikaru Hirose1, Yuji Hatano1, Akira Taguchi1, Tatsuya Hinoki2 (1. Univ. of Toyama, 2. Kyoto Univ.)

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

Development of tritium (T) removal technique from plasma-facing components is necessary for safe and cost-effective disposal of wastes, and it is important to understand the influence of radiation-induced damages on T release. In this study, W samples were damaged by 6.4 MeV Fe ions, and T release at 200-350 ℃ was examined under Ar gas flow. A majority of T was released as HTO/DTO, and the fraction of T released as HT/DT was less than 0.5%. Although total release rate of T from the sample increased with increasing temperature, only a minor portion of T was released after heating at 350 °C for 9 h. T release rate was controlled by diffusion of T in the damaged zone.