大矢恭久

オオヤヤスヒサ | YASUHISA OYA

所属機関・部署：
職名：准教授
ホームページURL (1件)： http://fusion.sci.shizuoka.ac.jp

研究分野 (1件)：エネルギー化学

研究キーワード (3件)：表面分析化学 , 放射化学 , トリチウム

競争的資金等の研究課題 (8件)：

全件表示

論文 (224件)：

F. Sun, D.Y. Chen, Q.H. Liu, J.P. Zhu, X.C. Li, H.S. Zhou, Y. Oya, L.M. Luo, Y.C. Wu. Competitive barrier and trapping effects of helium bubbles on hydrogen isotopes migration behavior in tungsten. Journal of Nuclear Materials. 2024. 155197
Y.J. Huang, C. Hao, Q.H. Liu, J.P. Zhu, F. Sun, Y. Oya, Y.C. W. Influence of helium bubbles location on hydrogen isotope retention and exchange behavior in plasma-facing materials: A numerical simulation investigation. Nuclear Materials and Energy. 2024. 101596
Baiyun Cheng, Qilai Zhou, Shengming Yin, Kaixuan Zhu, Yasuhisa Oya. abrication, sintering behavior, and strength of tritium breeding ceramic pebbles with Pb addition. Ceramics International. 2024. 27389-27402
F. Sun, C. Hao, D.Y. Chen, H.S. Zhou, Y. Oya, J.P.Zhu, J. Tang, H. Zong, L.M. Luo, Y.C. Wu. Mechanism of hydrogen isotope exchange for tritium removal in plasma-facing materials: a multi-scale investigation. Nuclear Fusion. 2024. 046011
Masayuki Tokitani, Mitsutaka Miyamoto, Suguru Masuzaki, Yuji Hatano, Sun Eui Lee, Yasuhisa Oya, Hironori Kurotaki, Nobuyuki Asakura, Hirofumi Nakamura, Takumi Hayashi, et al. Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures. Nuclear Materials and Energy. 2024. 39. 101678-101678

MISC (7件)：

特許 (2件)：

書籍 (6件)：

講演・口頭発表等 (37件)：

Synergistic effects of bulk/surface helium and irradiation damage on hydrogen isotope retention behavior in plasma facing materials (PFMs)
(APSOT-3 2020)
Evaluation of hydrogen retention behavior of damaged tungsten exposed to hydrogen plasma at QUEST with high temperature wall
(3rd Asia Pacific Symposium on Tritium Science 2020)
Protective behavior of tea catechins on DNA double strand breaks by radiations with different Linear Energy Transfer (LET)
(3rd Asia Pacific Symposium on Tritium Science 2020)
Influence of He and/or irradiation defects on the plasma driven permeation behavior in tungsten material
(3rd Asia Pacific Symposium on Tritium Science 2020)
Overview of hydrogen isotope retention characteristics for plasma facing walls after exposure in 2015-2019 QUEST plasma
(19th International Toki Conference (ITC-19) 2020)

学歴 (4件)：

学位 (1件)：

経歴 (2件)：

委員歴 (2件)：

受賞 (4件)：

所属学会 (5件)：

日本アイソトープ協会 , 日本科学教育学会 , 日本放射化学会 , プラズマ・核融合学会 , 日本原子力学会

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大矢 恭久