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[会议论文] 作者：Akira Hasegawa,Makoto Fukuda,Naoki Ebisawa,Takeshi Toyama,Taehyun Hwang,Shuhei Nogami,Yasuyoshi Nagai,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
Material property degradation of Tungsten(W)by neutron irradiation is one of key issues for plasma facing components in fusion power reactor.Displacement damage will cause irradiation hardening and em...
The damage depth profile effect on hydrogen isotope retention behavior in heavy ion irradiated tungs
[会议论文] 作者：Hiroe Fujita,Shodai Sakurada,Yuki Uemura,Keisuke Azuma,Qilai Zhou,Takeshi Toyama,Naoaki Yoshida,Yuji,
来源：第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) 年份：2016
The irradiation defects will be introduced to plasma facing materials,especially tungsten(W)by both energetic ions and 14 MeV neutrons produced by fusion reaction,where hydrogen isotopes would be stab...
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