2019 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1O01-07] Tungsten Materials (Behavior of Hydrogen Isotope)

Wed. Mar 20, 2019 10:00 AM - 11:55 AM Room O (Common Education Bildg. 2 4F No.46)

Chair:Takeshi Toyama(Tohoku Univ.)

10:30 AM - 10:45 AM

[1O03] Defect distribution influence on retention behavior in deuterium plasma implanted tungsten irradiated by neutron and Fe ion

*Shota Yamazaki1, Akihiro Togari2, Moeko Nakata2, Mingzhong Zhao2, Fei Sun1, Tatsuya Kuwabara3, Yuji Hatano4, Takeshi Toyama5, Yasuhisa Oya2 (1. Fac. Sci., Shizuoka Univ., 2. Grad. Sch. Sci. Tech., Shizuoka Univ., 3. Grad. Sch. Eng., Nagoya Univ., 4. HIRC, Univ. of Toyama, 5. IMR, Tohoku Univ.)

Keywords:plasma exposure, neutron irradiation, Thermal Desorption Spectrometry, tungsten, heavy ion irradiation

To understand effect of defect distribution on deuterium (D) retention behavior, tungsten (W) were irradiated by neutron and iron (Fe) ion. Afterwards, D2+ implantation and Thermal Desorption Spectrometry (TDS) were performed. D retention of neutron-Fe irradiated sample was lower than that of only Fe irradiated sample, indicating D retention behavior was associated with damage distribution.