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[会议论文] 作者:Yuji Hatano,Vladimir Kh.Alimov,Naoaki Yoshida,Makoto Oyaidzu,Takumi Hayashi,Masayuki Tokitani, 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
Reduced activation ferritic/martensitic(RAFM)steels such as F82H,EUROFER,RUSFER,CLAM and CLF-1 are structural material candidates of breeding blankets in future fusion reactors.The surface of RAFM ste...
[会议论文] 作者:Hiroki Tanaka,Mizuki Sakamoto,Hideo Watanabe,Masayuki Tokitani,Naoko Ashikawa,Shuntaro Ino,Akihiro Terakado, 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
Enhancement of hydrogen isotope retention in tungsten due to neutron irradiation is one of the most important issues for a future fusion device.In this study,properties of deuterium retention in recry...
[期刊论文] 作者:Miyuki YAJIMA,Masato YAMAGIWA,Shin KAJITA,Noriyasu OHNO,Masayuki TOKITANI,Arimichi TAKAYAMA,Seiki SAITO, 来源:Plasma Science and Technology 年份:2013
Tungsten was exposed to pure Ar or Ne plasmas over 1550 K at several incident ion energies.Even under the irradiation condition that the tungsten nanostructure...
[会议论文] 作者:,Hitoshi Tamura,Junichi Miyazawa,Teruya Tanaka,Ryuichi Sakamoto,Juro Yagi,Sadatsugu Takayama,Masayuki Tokitani, 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 conceptual design activity of the LHD-type helical reactor FFHR-d1 is being intensively conducted under the Fusion Engineering Research Project FERP at NIFS.The present activity incorporates the m...
[会议论文] 作者:Yasuhisa Oya,Cui Hu,Hiroe Fujita,Yuki Uemura,Shodai Sakurada,Keisuke Azuma,Miyuki Yajima,Masayuki Tokitani, 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
Tungsten(W),which possesses higher energy threshold for sputtering,low ability to hydride formation and low hydrogen solubility level,has been selected as the most likely candidate of plasma facing ma...
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