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Researcher DataBase - Personal Information :
OYA YASUHISA
Academic conference/research presentations
[1]. Synergistic effects of bulk/surface helium and irradiation damage on hydrogen isotope retention behavior in plasma facing materials (PFMs)
APSOT-3 （2020/11/3） invited
[Presenter]Fei Sun, Yasuhisa Oya
[2]. Influence of He and/or irradiation defects on the plasma driven permeation behavior in tungsten material
3rd Asia Pacific Symposium on Tritium Science （2020/11/） other
[Presenter]Mingzhong Zhao, Yasuhisa Oya
[3]. 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 （2020/11/） other
[Presenter]Takuro Wada, Yasuhisa Oya
[4]. 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 （2020/11/） other
[Presenter]Ayaka Koike, Yasuhisa Oya
[5]. Evaluation of hydrogen retention behavior of Damaged Tungsten exposed to hydrogen plasma at QUEST with High Temperature Wall
Nuclear Material Conference 2020 （2020/10/） other
[Presenter]Ayaka Koike, Yasuhisa Oya
[6]. Overview of hydrogen isotope retention characteristics for plasma facing walls after exposure in 2015-2019 QUEST plasma
19th International Toki Conference (ITC-19) （2020/10/） invited
[Presenter]Yasuhisa OYA, Ayaka KOIKE, Fei SUN, Naoaki YOSHIDA, Kazuaki HANADA
[7]. Impact of surface helium on hydrogen isotopes retention behavior in tungsten materials
日本原子力学会秋の大会 （2020/9/） other
[Presenter]孫飛、大矢恭久
[8]. 照射欠陥導入タングステンへの 重水素プラズマ照射による 滞留挙動に及ぼす照射温度依存性
日本原子力学会秋の大会 （2020/9/） other
[Presenter]山崎翔太、大矢恭久
[9]. QUEST2019S/Sでの水素プラズマ 曝露による水素同位体滞留に及ぼす 照射損傷影響評価
日本原子力学会秋の大会 （2020/9/） other
[Presenter]小池彩華、大矢恭久
[10]. Temperature Dependence on Deuterium Retention on Damaged Tungsten by Deuterium Plasma Exposure
3rd Asia Pacific Symposium on Tritium Science （2020/6/） other
[Presenter]Shota Yamazaki, Yasuhisa Oya
[11]. 表面／バルクに存在するヘリウムが水素同位体滞留に及ぼす影響
プラズマ核融合学会 （2020/6/） other
[Presenter]大矢恭久、孫飛
[12]. 大学間連携を活用した放射線安全教育プログラムの実践と今後の展開
日本原子力学会秋の大会 （2020/6/） other
[Presenter]大矢恭久、奥野健二
[13]. 欠陥導入 W における水素同位体同時照射が及ぼす重水素滞留挙動
プラズマ核融合学会 （2020/6/） other
[Presenter]齋藤巧、大矢恭久
[14]. タングステンにおけるH-D混合プラズマ駆動透過 に及ぼす水素同位体効果
プラズマ核融合学会 （2020/6/） other
[Presenter]芦沢京祐、大矢恭久
[15]. トリチウム増殖Li4SiO4−Li2TiO3 混合セラミック材からの トリチウム回収挙動
プラズマ核融合学会 （2020/6/） other
[Presenter]平田詩織、大矢恭久
[16]. タングステン－10%レニウム合金における重水素透過に関する研究
プラズマ核融合学会 （2020/6/） other
[Presenter]小山優輝、大矢恭久
[17]. 欠陥導入タングステン－10%レニウム合金における重水素滞留挙動に及ぼす照射温度影響
プラズマ核融合学会 （2020/6/） other
[Presenter]猪爪菜央、大矢恭久
[18]. Effect of deuterium-helium mixed plasma exposure on hydrogen isotopes retention in damaged tungsten
Nuclear Material Conference 2020 （2020/6/） other
[Presenter]Yasuhisa Oya
[19]. Overview of PHENIX Task 3 Activities for Tritium Behavior in High-temperature Neutron-irradiated Tungsten
ICFRM-19 （2019/10/30） invited
[Presenter]Yasuhisa Oya
[20]. SURFACE OR BULK HE EXSTENCE EFFECT ON DEUTERIUM RETENTION IN FE ION DAMAGED W
18th International Conference on Fusion Reactor Materials (ICFRM-18) （2018/11/） other
[Presenter]大矢 恭久
[Notes] Aomori, Japan
[21]. Correlation of surface chemical states with hydrogen isotope retention in divertor tiles of JET with ITER-Like Wall
2nd Asia-Pacific Symposium on Tritium Science (APSOT-2) （2018/9/） other
[Presenter]大矢 恭久
[Notes] Livermore, California, USA
[22]. Analyses of Structure, Composition and Retention of Hydrogen Isotopes in the JET-ILW Divertor Tiles
16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16) （2018/5/） invited
[Presenter]増崎 貴,大矢恭久
[Notes] Neuss/Düsseldorf, Germany
[23]. Removal of retained tritium in C-W mixed materual layer on tungsten by deuterium gas exposure
16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16) （2018/5/） other
[Presenter]戸苅陽大,大矢恭久
[Notes] Neuss/Düsseldorf, Germany
[24]. He irradiation effect on D permeation for W
ITPA meeting （2018/2/） other
[Presenter]大矢 恭久
[Notes] Chengdu, China
[25]. Hydrogen isotope retention enhancement for QUEST high temperature wall by long duration hydrogen plasma operation
16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16) （2017/1/） other
[Presenter]大矢 恭久
[Notes] Neuss/Düsseldorf, Germany
[26]. Interaction of hydrogen isotopes with radiation damaged tungsten
Inter-Academia2017 （2017/1/） other
[Presenter]大矢 恭久
[Notes] ルーマニア
[27]. Radiation exposure effect on deuterium retention in SiC
29th Symposium on Fusion Technology （2017/1/） other
[Presenter]大矢 恭久
[Notes] Prague, Czech Republic
[28]. Effect of defect concentration and distribution on hydrogen isotope retention and diffusion in damaged W for fusion first wall
Fusion Energy Conference 2016 （2016/10/） other
[Presenter]大矢 恭久
[29]. Influence of mixed material layer formation on hydrogen isotope retention in W exposed to 2014 LHD experiment campaign
China-Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering (CJS-13) （2016/9/） other
[Presenter]大矢 恭久
[Notes] Hefei, China
[30]. He retention in W exposed in LHD during 2014 plasma experimental campaign
Technology of Fusion Energy （2016/8/） other
[Presenter]大矢 恭久
[31]. Development of H, D, T simultaneous TDS measurement system and H, D, T retention behavior for DT gas exposed tungsten installed in LHD plasma campaign
Tritium Conference 2016 （2016/4/） other
[Presenter]大矢 恭久
[32]. Recent progress of hydrogen isotope behavior studies for neutron- and heavy ion-damaged W
1st Asia-Pacific Symposium on Tritium Science （2015/11/） invited
[Presenter]大矢 恭久
[Notes] Mianyang, China
[33]. タングステン材料中におけるトリチウムダイナミックス
日本原子力学会「2015年秋の大会」材料部会企画セッション （2015/9/） invited
[Presenter]大矢 恭久
[Notes] 日本原子力学会材料部会
[34]. 炭化系セラミックス材料における高エネルギーイオンのホットアトム化学的過程に関する研究
会議名(2010日本放射化学会) （2010/9/） invited
[Presenter]大矢 恭久
[Notes] 主催団体名(日本放射化学会) 開催地（大阪大学）
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