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[会议论文] 作者：Makoto Kobayashi,Kenji Okuno,Yasuhisa Oya,Rie Kurata,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Yasuhisa Oya,Rie Kurata,Makoto Kobayashi,Kenji Okuno,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Seira Horikoshi,Jumpei Mochizuki,Qilai Zhou,Yasuhisa Oya,Takumi Chikada,
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
According to the fusion blanket concepts with liquid tritium breeding materials,the development of a functional coating as a tritium permeation barrier with corrosion resistance is required.In our pre...
Deuterium permeation measurement of reduced activation ferritic/martensitic steel with yttrium oxide
[会议论文] 作者：Takumi Chikada,Jan Engels,Anne Houben,Jumpei Mochizuki,Seira Horikoshi,Yasuhisa Oya,
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
Fabrication of a thin ceramic coating as a tritium permeation barrier on structural materials is a promising solution to mitigate tritium loss in fusion fuel breeding/recovery systems.Yttrium oxide(Y2...
[会议论文] 作者：Naoko Ashikawa,Akio Sagara,Guangnan Luo,Yasuhisa Oya,Kenji Okuno,Makoto Kobayashi,Rie Kurata,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Kenji Okuno,Makoto Kobayashi,Rie Kurata,Naoko Ashikawa,Akio Sagara,Guangnan Luo,Yasuhisa Oya,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Kenji Okuno,Katsushi Matsuoka,Wanjing Wang,Rie Kurata,Makoto Kobayashi,Akiko Hamada,Yasuhisa Oya,Naoko,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Katsushi Matsuoka,Wanjing Wang,Rie Kurata,Makoto Kobayashi,Akiko Hamada,Naoko Ashikawa,Akio Sagara,Yasuhisa Oya,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Makoto Kobayashi,Kenji Okuno,Wanjing Wang,Rie Kurata,Junya Osuo,Masato Suzuki,Yasuhisa Oya,Toshiyuki,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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[会议论文] 作者：Okuno,Wanjing Wang,Rie Kurata,Junya Osuo,Masato Suzuki,Toshiyuki Fujii,Hajimu Yamaha,Kaiming Feng,Yasuhisa Oya,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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The damage depth profile effect on hydrogen isotope retention behavior in heavy ion irradiated tungs
[会议论文] 作者：,Yuki Uemura,Keisuke Azuma,Qilai Zhou,Takeshi Toyama,Naoaki Yoshida,Yuji Hatano,Takumi Chikada,Yasuhisa Oya,
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...
[会议论文] 作者：Wanjing Wang,Yasuhisa Oya,Kenji Okuno,Makoto Kobayashi,Rie Kurata,Junya Osuo,Masato Suzuki,Akiko Hamada,
来源：第三届中日氚和增值包层技术研讨会 年份：2010
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Influence of mixed material layer formation on hydrogen isotope retention in W exposed to 2014 LHD e
[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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