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 (216件)：

Yasuhisa Oya, Kyosuke Ashizawa, Fei Sun, Shiori Hirata, Naoko Ashikawa, Yoji Someya, Yuji Hatano, Robert Kolasinski, Chase N. Taylor, Masashi Shimada. Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure. Fusion Engineering and Design. 2023. 113722
Guangfan Tan, Liang Cai, Haifeng Xue, Xin Hu, Xiaoxu Dong, Hangyu Jiang, Xiuhong Yang, Yasuhisa Oya, Yingchun Zhang. Fabrication of porous Li4SiO4 ceramic sorbent pebbles with high CO2 sorption capacity via the simple freeze-drying method. Separation and Purification Technology. 2022. 123343
Chase N. Taylor, Masashi Shimada, Yuji Nobuta, Makoto I. Kobayashi, Yasuhisa Oya, Yuji Hatano. Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment. Nuclear Materials and Energy. 2022. 101323
Qilai Zhou, Fei Sun, Shiori Hirata, Sicheng Li, Yuanyuan Li, Yasuhisa Oya. Effect of neutron dose on the tritium release behavior of Li2TiO3-0.5Li4SiO4 biphasic ceramic. nternational Journal of Hydrogen Energy. 2022. 4363-4370
Qiao Wang, Qilai Zhou, Qingbi Xiong, Jianglin Zhou, Sicheng Li, Shiori Hirata, Yasuhisa Oya. Preparation of Li2TiO3-Li4SiO4-Pb tritium breeding ceramic and its mechanical properties. Ceramics International. 2022. 26742-26749

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 (4件)：

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