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静岡大学教員データベース - 教員個別情報 : 大矢 恭久 (OYA YASUHISA)

論文 等

【論文 等】
[1]. Mechanism of hydrogen isotope exchange for tritium removal in plasma-facing materials: a multi-scale investigation
Nuclear Fusion 64/ 046011- (2024年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] F. Sun, C. Hao, D.Y. Chen, H.S. Zhou, Y. Oya, J.P.Zhu, J. Tang, H. Zong, L.M. Luo and Y.C. Wu
[2]. Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures
Nuclear Materials and Energy 39/ 101678- (2024年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Masayuki Tokitani, Mitsutaka Miyamoto, Suguru Masuzaki, Yuji Hatano, Sun Eui Lee, Yasuhisa Oya, Hironori Kurotaki, Nobuyuki Asakura, Hirofumi Nakamura, Takumi Hayashi, Marek Rubel, Anna Widdowson, Jari Likonen, JET Contributors
[3]. abrication, sintering behavior, and strength of tritium breeding ceramic pebbles with Pb addition
Ceramics International 50/ 27389-27402 (2024年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Baiyun Cheng, Qilai Zhou, Shengming Yin, Kaixuan Zhu, Yasuhisa Oya
[4]. Influence of helium bubbles location on hydrogen isotope retention and exchange behavior in plasma-facing materials: A numerical simulation investigation
Nuclear Materials and Energy 38/ 101596- (2024年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Y.J. Huang, C. Hao, Q.H. Liu, J.P. Zhu, F. Sun, Y. Oya, Y.C. W
[5]. Competitive barrier and trapping effects of helium bubbles on hydrogen isotopes migration behavior in tungsten
Journal of Nuclear Materials 599/ 155197- (2024年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] 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
[6]. Tritium and deuterium release behavior of Li2TiO3-0.5Li4SiO4–Pb ceramic
Ceramics International 49/ 26778-267895 (2023年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Qilai Zhou, Sicheng Li, Shiori Hirata, Asahi Sanfukuji, Guangfan Tan, Akira Taguchi, Yasuhisa Oya
[7]. Estimation of different calculation models for evaluating heavy ion-induced damage in plasma facing materials
Fusion Engineering and Design 194/ 113910- (2023年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] F. Sun, D.Y. Chen, C. Hao, Y. Oya, J.P. Zhu, D.D. Li, L.M. Luo, Y.C. Wu
[8]. Thermal annealing effect on D retention for damaged W-10%Re alloy
Fusion Engineering and Design 196/ 113981- (2023年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] Yasuhisa Oya, Nao Inozume, Yuzuka Hoshino, Naoaki Yoshida, Tatsuya Hinoki, Kiyohiro Yabuuchi, Yuji Hatano, Qilai Zhou, Fei Sun, Robert Kolasinski, Chase N. Taylor, Masashi Shimad
[9]. Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure
Fusion Engineering and Design 194/ 113722- (2023年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] Yasuhisa Oya, Kyosuke Ashizawa, Fei Sun, Shiori Hirata, Naoko Ashikawa, Yoji Someya, Yuji Hatano, Robert Kolasinski, Chase N. Taylor, Masashi Shimada
[10]. Effect of rhenium addition on deuterium retention in neutron-irradiated tungsten
Journal of Nuclear Materials 566/ 153774- (2022年) [査読] 無 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Y. Nobuta, T. Toyama, A. Matsumoto, M. Shimada, Y. Oya, K. Inoue, Y. Nagai, Y. Hatano
[11]. Preparation of Li2TiO3-Li4SiO4-Pb tritium breeding ceramic and its mechanical properties
Ceramics International 48/ 26742-26749 (2022年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Qiao Wang, Qilai Zhou, Qingbi Xiong, Jianglin Zhou, Sicheng Li, Shiori Hirata, Yasuhisa Oya
[12]. Tritium recovery behavior for tritium breeder Li4SiO4-Li2TiO3 biphasic material
Journal of Nuclear Materials 567/ 153838- (2022年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] Shiori Hirata, Kyosuke Ashizawa, Fei Sun, Yongjin Feng, Xiaoyu Wang, Hailiang Wang, Makoto Kobayashi, Akira Taguchi, Yasuhisa Oya
[13]. Effect of neutron dose on the tritium release behavior of Li2TiO3–0.5Li4SiO4 biphasic ceramic
nternational Journal of Hydrogen Energy 48/ 4363-4370 (2022年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Qilai Zhou, Fei Sun, Shiori Hirata, Sicheng Li, Yuanyuan Li, Yasuhisa Oya
[14]. Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment
Nuclear Materials and Energy 34/ 101323- (2022年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Chase N. Taylor, Masashi Shimada, Yuji Nobuta, Makoto I. Kobayashi, Yasuhisa Oya, Yuji Hatano
[15]. Fabrication of porous Li4SiO4 ceramic sorbent pebbles with high CO2 sorption capacity via the simple freeze-drying method
Separation and Purification Technology 311/ 123343- (2022年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Guangfan Tan, Liang Cai, Haifeng Xue, Xin Hu, Xiaoxu Dong, Hangyu Jiang, Xiuhong Yang, Yasuhisa Oya, Yingchun Zhang
[16]. Evaluation of Hydrogen Retention Behavior for Damaged Tungsten Exposed to Hydrogen Plasma at QUEST with High Temperature Wall
Fusion Engineering and Design 176/ 113020- (2022年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] Ayaka Koike, Shota Yamazaki, Takuro Wada, Fei Sun, Naoaki Yoshida, Kazuaki Hanada, Yasuhisa Oya
[17]. Evaluation of hydrogen retention behavior in tungsten exposed to hydrogen plasma in QUEST
Nuclear Materials and Energy 26/ 100856- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Ayaka Koike, Moeko Nakata, Shota Yamazaki, Takuro Wada, Fei Sun, Mingzhong Zhao, Naoaki Yoshida, Kazuaki Hanada, Yasuhisa Oya
[18]. Investigation on tritium retention and surface properties on the first wall in the large helical Device
Nuclear Materials and Energy 27/ 100906- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] M. Yajima, S. Masuzaki, N. Yoshida, M. Tokitani, T. Otsuka, Y. Oya, Y. Torikai, G. Motojima, the LHD Experiment Group
[19]. Protective behavior of tea catechins against DNA double strand breaks produced by radiations with different liner energy transfer
Fusion Engineering and Design 172/ 112700- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Takuro Wada, Ayaka Koike, Shota Yamazaki, Kyosuke Ashizawa, Fei Sun, Yuji Hatano, Hiroto Shimoyachi, Takahiro Kenmotsu, Takashi Ikka, Yasuhisa Oya
[20]. Cesium uptake and translocation from tea cutting roots (Camellia sinensis L.)
Journal of Environmental Radioactivity 235-236/ 106655- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Hiroto Yamashita, Yoshifumi Nishina, Naho Komori, Mizuho Kamoshita, Yasuhisa Oya, Kenji Okuno, Akio Morita, Takashi Ikka
[21]. Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST
Nuclear Materials and Energy 27/ 101013- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] K. Hanada, N. Yoshida, M. Hasegawa, M. Oya, Y. Oya, I. Takagi, A. Hatayama, T. Shikama, H. Idei, Y. Nagashima, R. Ikezoe, T. Onchi, K. Kuroda, S. Kawasaki, A. Higashijima, T. Nagata, S. Shimabukuro, K. Nakamura, S. Murakami, Y. Takase, X. Gao, H. Liu, J. Qian
[22]. Numerical analysis of deuterium migration behaviors in tungsten damaged by fast neutron by means of gas absorption method
Fusion Engineering and Design 168/ 112635- (2021年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Makoto I Kobayashi, Masashi Shimada, Chase N Taylor, Yuji Nobuta, Yuji Hatano, Yasuhisa Oya
[23]. Neutron irradiated tungsten bulk defect characterization by positron annihilation spectroscopy
Nuclear Materials and Energy 26/ 100936- (2021年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Chase N. Taylor, Masashi Shimada, Joseph M. Watkins, Xunxiang Hu, Yasuhisa Oya
[24]. Global distribution of tritium in JET with the ITER-like wall
Nuclear Materials and Energy 26/ 100930- (2021年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] S.E. Lee, Y. Hatano, M. Tokitani, S. Masuzaki, Y. Oya, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, K. Isobe, H. Kurotaki, D. Hamaguchi, T. Hayashi, A. Widdowson, S. Jachmich, J. Likonen, M. Rubel, JET contributors
[25]. Evaluation of hydrogen retention behavior in tungsten exposed to hydrogen plasma in QUEST
Nuclear Materials and Energy 26/ 100856- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Ayaka Koike, Moeko Nakata, Shota Yamazaki, Takuro Wada, Fei Sun, Mingzhong Zhao, Naoaki Yoshida, Kazuaki Hanada, Yasuhisa Oya
[26]. Investigation on tritium retention and surface properties on the first wall in the large helical Device
Nuclear Materials and Energy 27/ 100906- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] M. Yajima, S. Masuzaki, N. Yoshida, M. Tokitani, T. Otsuka, Y. Oya, Y. Torikai, G. Motojima, the LHD Experiment Group
[27]. Effects of irradiation temperature on tritium retention in stainless steel type 316L
Fusion Engineering and Design 169/ 112436- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Masao Matsuyama, Hideki Zushi, Kazuaki Hanada, Yasuhisa Oya, Yuji Hatano
[28]. Deuterium recombination coefficient on tungsten surface determined by plasma driven permeation
Fusion Engineering and Design 160/ 111853- (2021年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Mingzhong Zhao, Shota Yamazaki, Takuro Wada, Ayaka Koike, Fei Sun, Naoko Ashikawa, Yoji Someya, Tetsu Mieno, Yasuhisa Oya
[29]. Comparison of hydrogen isotope retention in divertor tiles of JET with the ITER-Like Wall following campaigns in 2011-2012 and 2015-2016
Fusion Science and Technology 76/ 439-445 (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] Yasuhisa Oya, Suguru Masuzaki, Masayuki Tokitani, Moeko Nakata, Fei Sun, Makoto Oyaidzu, Kanetsuku Isobe, Nobuyuki Asakura, Teppei Otsuka, Anna Widdowson, Jari Likonen, Marek Rubel and JET contributors
[30]. D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation
Journal of Nuclear Materials 539/ 152323- (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] Y. Oya, F. Sun, Y. Yamauchi, Y. Nobuta, M. Shimada, C.N. Taylor, W.R. Wampler, M. Nakata, L.M. Garrison, and Y. Hatano
[31]. Comparison of tritium release behavior in Li2TiO3 and promising core- shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles
Journal of Nuclear Materials 539/ 152300- (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Qiang Qi, Jing Wang, Qilai Zhou, Yingchun Zhang, Mingzhong Zhao, Shouxi Gu, Moeko Nakata, Haishan Zhou, Yasuhisa Oya, Guang-Nan Luo
[32]. Changes in surface morphology of helium-induced tungsten nanostructure during high-temperature annealing
Nuclear Materials and Energy 22/ 100730- (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Chun-Shang Wong, Josh A. Whaley, Takuro Wada, Sakumi Harayama, Yasuhisa Oya, Robert D. Kolasinski
[33]. Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry
Fusion Engineering and Design 160/ 111959- (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] S.E. Lee, Y. Hatano, M. Hara, S. Masuzaki, M. Tokitani, M. Oyaizu, H. Kurotaki, D. Hamaguchi, H. Nakamura, N. Asakura, Y. Oya, J. Likonen, A. Widdowson, S. Jachmich, K. Helariutta, M. Rubel, JET Contributors
[34]. Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method
Fusion Science and Technology 76/ 246-251 (2020年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Mingzhong Zhao, Moeko Nakata, Fei Sun, Yuji Hatano, Yoji Someya, Kenji Tobita, Yasuhisa Oya [DOI]
[35]. Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature
International Journal of Hydrogen Energy 45/ 9959-9968 (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Qilai Zhou, Akihiro Togari, Moeko Nakata, Mingzhong Zhao, Fei Sun, Miyuki Yajima, Masayuki Tokitani, Suguru Masuzaki, Naoaki Yoshida, Masanori Hara, Yuji Hatano, Yasuhisa Oya
[36]. Investigation of remaining tritium in the LHD vacuum vessel after the first deuterium experimental campaign
Physica Scripta T171/ 014068- (2020年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] S. Masuzaki, T. Otsuka, K. Ogawa, M. Yajima, M. Tokitani, Q. Zhou, M. Isobe, Y. Oya, N. Yoshida, Y. Nobuta and the LHD Experimental Group
[37]. Development of Plasma Driven Permeation Measurement System for Plasma Facing Materials
Engineering for Sustainable Future. INTER-ACADEMIA 2019. Lecture Notes in Networks and Systems 101/ 260-268 (2020年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Mingzhong Zhao, Shota Yamazaki, Moeko Nakata, Fei Sun, Takuro Wada, Ayaka Koike, Yoji Someya, Kenji Tobita, Yasuhisa Oya
[38]. Synergistic effects of high energy helium irradiation and damage introduction at high temperature on hydrogen isotope retention in plasma facing materials
Journal of Nuclear Materials 533/ 152122- (2020年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] F. Sun, M. Nakata, S. E. Lee, M. Zhao, T. Wada, S. Yamazaki, A. Koike, S. Kondo, T. Hinoki, M. Hara, Y. Oya
[39]. Hydrogen isotope exchange at the surface of C-W mixed material layer on tungsten by gas exposure
Fusion Engineering and Design 157/ 111633- (2020年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] Yasuhisa Oya, Akihiro Togari, Moeko Nakata, Ayaka Koike, Takuro Wada, Shota Yamazaki, Mingzhong Zhao, Fei Sun, Miyuki Yajima, Suguru Masuzaki
[40]. Modeling and simulation for surface helium effect on hydrogen isotopes diffusion and trapping/detrapping behavior in plasma facing materials
Journal of Nuclear Materials 537/ 152227- (2020年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] F. Sun, X.C. Li, L. Zhang, M. Nakata, M. Zhao, T. Wada, S. Yamazaki, A. Koike, Y. Oya
[41]. Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron
Fusion Engineering and Design 146/ 1624-1627 (2019年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] M. Kobayashi
[42]. Effect of carbon impurity reduction on hydrogen isotope retention in QUEST high temperature wall
Fusion Engineering and Design 146/ 1480-1484 (2019年) [査読] 無 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] Y. Oya
[43]. Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution
Fusion Engineering and Design 146/ 2096-2099 (2019年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] M. Nakata
[44]. Kinetics of double strand breaks of DNA in tritiated water evaluated using single molecule observation method
Fusion Engineering and Design 146/ 100-102 (2019年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] Y. Hatano
[45]. Release kinetics of tritium generation in neutron irradiated biphasic Li2TiO3-Li4SiO4 ceramic breeder
Journal of Nuclear Materials 522/ 286-293 (2019年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] Q. Zhou
[46]. Estimation of fuel particle balance in steady state operation with hydrogen barrier model
Nuclear Materials and Energy 19/ 544-549 (2019年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] K. Hanada
[47]. Effect of Damage introduction and He existence on D retention in Tungsten by high flux D plasma exposure
Recent Advances in Technology Research and Education 53/ 89-96 (2018年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] Y. Oya
[48]. Surface or bulk He existence effect on deuterium retention in Fe ion damaged W
Nuclear Materials and Energy 16/ 217-220 (2018年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] Y. Oya
[49]. Radiation exposure effect on deuterium retention in SiC
Journal of Nuclear and Radiochemical Sciences 18/ 9-12 (2018年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] Y. Oya
[50]. Deuterium removal efficiency in Tugsten as a function of hydrogen ion beam fluence and temperature
ecent Advances in Technology Research and Education 53/ 20-27 (2018年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] M. Zhao
[51]. Interaction of hydrogen isotopes with radiation damaged tungsten
Advances in Intelligent Systems and Computing 660/ 41-49 (2018年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[52]. Helium retention behavior in simultaneously He+ -H2+ irradiated tungsten
Journal of Nuclear Materials 502/ 289-294 (2018年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] 周啓来
[53]. Correlation of surface chemical states with hydrogen isotope retention in divertor tiles of JET with ITER-Like Wall
Fusion Engineering and Design 132/ 24-28 (2018年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[54]. Effect of C-He simultaneous implantation on deuterium retention in damaged W by Fe implantation
Fusion Engineering and Design 137/ 10-14 (2018年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] 東啓介
[55]. Radiocesium uptake through leaf surfaces of tea plants (Camellia sinensis L.)
Journal of Environmental Radioactivity 182/(num) 70-73 (2018年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]一家崇 [共著者]大矢 恭久
[56]. Dependence of hydrogen-absorption and -desorption characteristics on density of lithium–zirconium oxides exposed in air at room temperature
Acta Materialia 148/(num) 185-192 (2018年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]土屋文 [共著者]大矢 恭久
[57]. Investigation of hydrogen recycling in long duration discharges and its modification with a hot wall in the spherical tokamak QUEST
Nuclear Fusion 57/12 126061- (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]花田和明 [共著者]大矢 恭久
[58]. Impact of Annealing on Deuterium Retention Behavior in Damaged W
Fusion Science and Technology 72/(num) 785-788 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]桜田翔大 [共著者]大矢 恭久
[59]. Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD
Nuclear Materials and Energy 12/(num) 483-487 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]信太祐二 [共著者]大矢 恭久
[60]. 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
Fusion Science and Technology 71/(num) 351-356 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[61]. Current Status of Large Helical Device and Its Prospect for Deuterium Experiment
Fusion Science and Technology 72/(num) 199-210 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]長壁正樹 [共著者]大矢 恭久
[62]. Influence of mixed material layer formation on hydrogen isotope and He retentions in W exposed to 2014 LHD experiment campaign
Fusion Engineering and Design 125/(num) 458-462 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[63]. Effect of sequential Fe2+-C+ implantation on deuterium retention in W
Fusion Engineering and Design 124/(num) 231-234 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]東奎介 [共著者]大矢 恭久
[64]. The damage depth profile effect on hydrogen isotope retention behavior in heavy ion irradiated tungsten
Fusion Engineering and Design 125/(num) 468-472 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]藤田啓恵 [共著者]大矢 恭久
[65]. Deuterium permeation behavior in iron-irradiated erbium oxide coating
Fusion Engineering and Design 124/(num) 915-918 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]近田拓未 [共著者]大矢 恭久
[66]. Deuterium permeation and retention behaviors in erbium oxide-iron multilayer coatings
Fusion Engineering and Design 124/(num) 1086-1090 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]堀越清良 [共著者]大矢 恭久
[67]. Deuterium permeation behavior of tritium permeation barrier coating containing carbide nanoparticles
Fusion Engineering and Design 124/(num) 1073-1076 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]望月淳平 [共著者]大矢 恭久
[68]. Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD
Nuclear Materials and Energy 12/ 483-487 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] Y. Nobuta
[69]. Deuterium retention in helium and neutron irradiated molybdenum
Fusion Science and Technology 71/(num) 491-495 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Chase Taylor [共著者]大矢 恭久
[70]. Hydrogen Isotope Retention and Permeation in Neutron-Irradiated Tungsten and Tungsten Alloys Under PHENIX Collaboration
Fusion Science and Technology 72/(num) 652-659 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]島田雅 [共著者]大矢 恭久
[71]. Progress in the U.S./Japan PHENIX Project for the Technological Assessment of Plasma Facing Components for DEMO Reactors
Fusion Science and Technology 72/(num) 222-232 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]加藤雄大 [共著者]大矢 恭久
[72]. Effect of helium irradiation on deuterium permeation behavior in tungsten
Journal of Nuclear Materials 490/(num) 242-246 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[73]. Preparation of Li2TiO3 ceramic with nano-sized pores by ultrasonic-assisted solution combustion
Journal of the European Ceramic Society 37/(num) 3595-3602 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]周 啓来 [共著者]大矢 恭久
[74]. Tritium trapping states induced by lithium-depletion in Li2TiO3
Journal of Nuclear Materials 487/(num) 84-90 (2017年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林真 [共著者]大矢 恭久
[75]. Micro-/nano-characterization of the surface structures on the divertor tiles from JET ITER-like wall
Fusion Engineering and Design 116/(num) 1-4 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]時谷政行 [共著者]大矢 恭久
[76]. Interaction of hydrogen isotopes with radiation damaged tungsten
Advances in Intelligent Systems and Computing 660/(num) 41-49 (2017年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[77]. Recent progress of hydrogen isotope behavior studies for neutron or heavy ion damaged W
Fusion Engineering and Design 113/(num) 211-215 (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[78]. High-flux plasma exposure of ultra-fine grain tungsten
International Journal of Refractory Metals and Hard Materials 60/(num) 28-36 (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Robert Kolasinski [共著者]大矢 恭久
[79]. Deuterium retention in molten salt electrodeposition tungsten coatings
Fusion Engineering and Design 113/(num) 265- 268 (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Hai-Shan Zhou [共著者]大矢 恭久
[80]. Dependence of CuO particle size and diameter of reaction tubing on tritium recovery for tritium safety operation
Fusion Engineering and Design 113/(num) 313-317 (2016年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]Cui Hu [共著者]大矢 恭久
[81]. Influence of carbon-dominated layer on He retention in W exposed in LHD during 2014 plasma experimental campaign
Fusion Engineering and Design 112/(num) 117-122 (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Cui Hu [共著者]大矢 恭久
[82]. Annealing effects on deuterium retention behavior in damaged tungsten
Nuclear Materials and Energy 9/(num) 141-144 (2016年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]桜田 翔大 [共著者]大矢 恭久
[83]. Crystallization and deuterium permeation behaviors of yttrium oxide coating prepared by metal organic decomposition
Nuclear Materials and Energy 9/(num) 529-534 (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]近田拓未 [共著者]大矢 恭久
[84]. Effect of impurity deposition layer formation on D retention in LHD plasma exposed W
Nuclear Materials and Energy 9/(num) 84-88 (2016年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[85]. Review of recent japanese activities on tritium accountability in fusion reactors
Fusion Engineering and Design 113/(num) 231-235 (2016年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]深田智 [共著者]大矢 恭久
[86]. Deuterium permeation behavior for damaged tungsten by ion implantation
Journal of Nuclear Science and Technology 53/(num) 402-405 (2016年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[87]. Impact of temperature during He+ implantation on deuterium retention in tungsten, tungsten with carbon deposit and tungsten carbide
Physica Scripta T167/(num) 014037- (zzz) (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[88]. Effect of neutron energy and fluence on deuterium retention behaviour in neutron irradiated tungsten
Physica Scripta T167/(num) 014067- (zzz) (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]藤田啓恵 [共著者]大矢 恭久
[89]. Gas-driven permeation of deuterium through tungsten and tungsten alloys
Fusion Engineering and Design 109-111/ 104-108 (2016年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Dean A. Buchenauer [共著者]大矢 恭久
[90]. Irradiation effect on deuterium behavior in low-dose HFIR neutron-irradiated tungsten
Nuclear Fusion 55/(num) 013008- (zzz) (2015年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Masashi Shimada [共著者]大矢 恭久
[91]. Thermal desorption behavior of deuterium for 6MeV Fe ion irradiated W with various damage concentrations
Journal of Nuclear Materials 461/(num) 336-340 (2015年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[92]. Preheating Temperature Effect on Tritium Retention in VPS-W
Fusion Science and Technology 67/(num) 551-554 (2015年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]佐藤美咲 [共著者]大矢 恭久
[93]. In-Situ Observation of Sputtered Particles for Carbon Implanted Tungsten During Energetic Hydrogen Isotope Ion Implantation
Fusion Science and Technology 67/(num) 515-518 (2015年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[94]. A multi-technique analysis of deuterium trapping and near-surface precipitate growth in plasma-exposed tungsten
Journal of Applied Physics 118/(num) 073301- (zzz) (2015年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]R. D. Kolasinski [共著者]大矢 恭久
[95]. Dynamics for HT and HTO recovery through eater bubbler and CuO catalyst
Fusion Science and Technology 68/(num) 358-361 (2015年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[96]. Effect of Heating Temperature on Deuterium Retention Behavior for Helium/Carbon Implanted Tungsten
Fusion Science and Technology 68/(num) 531-534 (2015年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]佐藤美咲 [共著者]大矢 恭久
[97]. Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten
Journal of Nuclear Materials 463/(num) 1005-1008 (2015年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Mavashi Shimada [共著者]大矢 恭久
[98]. Developing a tritium release model for Li2TiO3 with irradiation-induced defects
Journal of Nuclear Materials 458/(num) 22-28 (2015年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[99]. XPS investigation of impurities containing boron films affected by energetic deuterium implantation and thermal desorption
Journal of Nuclear Materials 457/(num) 118-123 (2015年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Shao Dadong [共著者]大矢 恭久
[100]. Dissolution behavior of 137Cs absorbed on the green tea leaves
Journal of Radioanalytical and Nuclear Chemistry 303/(num) 1539-1542 (2015年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[101]. Effects of helium and ambient water vapor on tritium release from Li2TiO3
Journal of Nuclear Materials 455/(num) 735-738 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[102]. LHDプラズマに曝されたタングステンにおける水素滞留能変化
プラズマ・核融合学会誌 90/(num) 319-324 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[103]. LHDプラズマに曝されたタングステンにおける水素同位体滞留能変化
プラズマ・核融合学会誌 90/6 319-324 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[104]. Dependency of irradiation damage density on tritium migration behaviors in Li2TiO3
Journal of Nuclear Materials 447/ 1-8 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[105]. Hydrogen isotope behavior on a water–metal boundary with simultaneous transfer from and to the metal surface
Fusion Engineering and Design 89/(num) 1520-1523 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]林 巧 [共著者]大矢 恭久
[106]. Comparison of hydrogen isotope retention for tungsten probes in LHD vacuum vessel during the experimental campaigns in 2011 and 2012
Fusion Engineering and Design 89/(num) 1091-1095 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[107]. Dependency of irradiation damage density on tritium migration behaviors in Li2TiO3
Journal of Nuclear Materials 447/(num) 1-8 (2014年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[108]. Deuterium trapping at defects created with neutron and ion irradiations in tungsten
Nuclear Fusion 53/ 073006- (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]波多野 雄治 [共著者]大矢 恭久
[109]. Migration of hydrogen isotopes in lithium metatitanate
Journal of Nuclear Materials 439/ 159-167 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[110]. Integrated Material System Modeling of Fusion Blanket
Materials Transactions 54/ 477-483 (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]相良 明男 [共著者]大矢 恭久
[111]. Behaviors of deuterium retention and microstructure change of tungsten simultaneously implanted with carbon and/or helium ions
Materials Transactions 54/ 430-436 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[112]. Retention of hydrogen isotopes in neutron irradiated tungsten
Materials Transactions 54/ 437-441 (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]波多野 雄治 [共著者]大矢 恭久
[113]. Tritium release kinetics in lithium orthosilicate ceramic pebbles irradiated with low thermal-neutron fluence
Journal of Nuclear Materials 438/ 46-50 (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Chengjian Xiao [共著者]大矢 恭久
[114]. Retention behavior of deuterium and oxygen in boronized VPS-W
Journal of Nuclear Materials 438/ S1138-S1141 (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]Wanjing Wang [共著者]大矢 恭久
[115]. Retention and desorption behavior of tritium in Si related ceramics
Journal of Nuclear Materials 438/ 22-25 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[116]. Detection of radioactive materials from the Fukushima Daiichi nuclear Power Plant accident at Shizuoka-city
Radiation Safety Management 12/ 16-21 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]矢永 誠人 [共著者]大矢 恭久
[117]. 核融合炉材料中のトリチウム移行過程の解明に向けたトリチウム測定技術
分析化学 62/ 99-105 (2013年) [査読] 無 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[118]. Formation of lithium-tritide by hot atom reactions of tritium produced in Pb-16Li
Fusion Engineering and Design 88/ 2328-2331 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]奥野 健二 [共著者]大矢 恭久
[119]. Deuterium trapping by irradiation damage in tungsten induced by different displacement processes
Fusion Engineering and Design 88/ 1749-1752 (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[120]. Study of correlation between tritium release behaviors and irradiation defects produced by electronic excitation process in Li2TiO3
Fusion Engineering and Design 88/ 2369-2372 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]戸田 健介 [共著者]大矢 恭久
[121]. Influence of tungsten-carbon mixed layer and irradiation defects on deuterium retention behavior in tungsten
Fusion Engineering and Design 88/ 1827-1830 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]三浦 遼 [共著者]大矢 恭久
[122]. Enhancement of Hydrogen Isotope Retention Capacity for the Impurity Deposited Tungsten by Long-term Plasma Exposure in LHD
Fusion Engineering and Design 88/ 1699-1703 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[123]. Behavior of deuterium retention and surface morphology for VPS-W/F82H
Journal of Nuclear Materials 442/(num) S242-S245 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[124]. Dynamic deuterium recycling on tungsten under carbon-deuterium implantation circumstance
Journal of Nuclear Materials 438/ S1117-S1120 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]田口 僚久 [共著者]大矢 恭久
[125]. Enhancement of hydrogen isotope retention in tungsten exposed to LHD plasmas
Journal of Nuclear Materials 438/ S1055-S1058 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[126]. Trapping of hydrogen isotopes in radiation defects formed in tungsten by neutron and ion irradiations
Journal of Nuclear Materials 438/ S114-S119 (2013年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]波多野 雄治 [共著者]大矢 恭久
[127]. Tritium retention on stainless steel surface exposed to Plasmas in LHD (II)
Plasma and Fusion Research 8/ 2405014- (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]松山 政夫 [共著者]大矢 恭久
[128]. Study on plasma – tungsten surface interactions using the new experimental device EXPRESS
Journal of Plasma and Fusion Research 10/ 85-88 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]三浦 遼 [共著者]大矢 恭久
[129]. Tritium release kinetics in lithium-enriched Li2+xTiO3 with thermal neutron irradiation
Journal of Plasma and Fusion Research 10/ 7-11 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[130]. Implantation energy dependence on deuterium retention behaviors for the carbon implanted tungsten
Journal of Plasma and Fusion Research 10/ 76-80 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[131]. Trapping of Tritium by Stainless Steel Exposed to Plasmas in Experimental Campaigns of LHD
Journal of Plasma and Fusion Research 10/ 64-70 (2013年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]松山 政夫 [共著者]大矢 恭久
[132]. Tritium Retention on Stainless Steel Surface Exposed to Plasmas in LHD (II)
Plasma and Fusion Research 7/ 2405091- (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]松山 政夫 [共著者]大矢 恭久
[133]. Kinetics of tritium release from thermal neutron-irradiated Li0.17Pb0.83
Fusion Science and Technology 62/ 56-60 (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[134]. Effect of surface oxide layer on deuterium permeation behaviors through a type 316 stainless steel
Fusion Engineering and Design 87/ 580-583 (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 責任著者
[著者] 大矢 恭久
[135]. Hydrogen isotope permeation from cooling water through various metal piping
Fusion Engineering and Design 87/ 1333-1337 (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]林 巧 [共著者]大矢 恭久
[136]. Release kinetics of tritium generated in lithium-enriched Li2+xTiO3 by thermal neutron irradiation
Fusion Engineering and Design 87/ 471-475 (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]小林 真 [共著者]大矢 恭久
[137]. Study on the retention behavior of hydrogen isotopes and the change of chemical states of boron film exposed hydrogen plasma in LHD
Fusion Engineering and Design 87/ 1214-1217 (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]濱田 明公子 [共著者]大矢 恭久
[138]. Overview of the US-Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten
Fusion Engineering and Design 87/ 1166-1170 (2012年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]島田 雅 [共著者]大矢 恭久
[139]. Measurement of deuterium and helium by glow-discharge optical emission spectroscopy for plasma–surface interaction studies
Fusion Engineering and Design 87/ 1091-1094 (2012年) [査読] 有 [国際共著論文] 該当する
[責任著者・共著者の別] 共著者
[著者] [責任著者]波多野 雄治 [共著者]大矢 恭久
[140]. デジタルツールとしてiPodを活用したエネルギー環境学習
エネルギー環境教育研究 6/ 3-10 (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]萱野 貴広 [共著者]大矢 恭久
[141]. Hydrogen Retention Behavior in Boron Films Affected by Impurities Introduced by Hydrogen Plasma Exposure in the LHD
Plasma and Fusion Research 7/ 2401157- (2012年) [査読] 有 [国際共著論文] 該当しない
[責任著者・共著者の別] 共著者
[著者] [責任著者]松岡 和志 [共著者]大矢 恭久
[142]. Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten
PHYSICA SCRIPTA T145/ 014050 (2011年)
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Masashi Shimada,Makoto Kobayashi,Takuji Oda,Masanori Hara,Hideo Watanabe,Yuji Hatano,Pattrick Calderoni,Kenji Okuno
[143]. Recent progress of tungsten R&D for fusion application in Japan
PHYSICA SCRIPTA T145/ 014029 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Ueda [共著者]H.T. Lee,N. Ohno,S. Kajita,A. Kimura,R. Kasada,T. Nagasaka,Y. Hatano,A. Hasegawa,H. Kurishita,Y. Oya
[144]. Deuterium depth profile in neutron-irradiated tungsten exposed to plasma
PHYSICA SCRIPTA T145/ 014051 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Masashi Shimada [共著者]G Cao,Y Hatano,Takuji Oda,Y Oya,M Hara,P Calderoni
[145]. Retention and desorption behaviors of hydrogen isotopes in gamma-ray irradiated Li2TiO3
FUSION SCIENCE AND TECHNOLOGY 60/1 399-402 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Akiko Hamada [共著者]Makoto Kobayashi,Rie Kurata,Masato Suzuki,Hajimu Yamana,Toshiyuki Fujii,Yasuhisa Oya,Kenji Okuno
[146]. Comparison of hydrogen isotope retention and irradiation damage behaviors in tungsten and SS-316 with simultaneous C+-D2+ implantation
FUSION ENGINEERING AND DESIGN 86/ 1776-1779 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Makoto Kobayashi,Rie Kurata,Naoaki Yoshida,Naoko Ashikawa,Akio Sagara,Masanori Hara,Yuji Hatano,Kenji Okuno
[147]. Hydrogen Isotope Behavior Transferring Through Water Metal Boundary
FUSION SCIENCE AND TECHNOLOGY 60/1 369-372 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Takumi Hayashi [共著者]Hirofumi Nakamura,Kanetsugu Isobe,Kazuhiro Kobayashi,Makoto Oyaizu,Yasuhisa Oya,Kenji Okuno,Toshihiko Yamanishi
[148]. First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE
JOURNAL OF NUCLEAR MATERIALS 415/ S728-S730 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Masashi Shimada [共著者]Y. Hatano,P. Calderoni,T. Oda,Y. Oya,M. Sokolov,K. Zhang,G. Cao,R. Kolasinski,J.P. Sharpe
[149]. Dependence of gamma-ray Dose on Annihilation Processes of Irradiation Defects in Li2TiO3
FUSION ENGINEERING AND DESIGN 86/ 2362-2364 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Junya Osuo [共著者]Makoto Kobayashi,Rie Kurata,Akiko Hamada,Wanjing Wang,Toshiyuki Fujii,Hajimu Yamana,Tianyong Luo,Kaiming Feng,Yasuhisa Oya,Kenji Okuno
[150]. Deuterium retention in SiC coated graphite by D2+ implantation
FUSION ENGINEERING AND DESIGN 86/ 1689-1692 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Qiang Li [共著者]Wanjing Wang,Zhongshi Yang,Kenji Okuno,Yasuhisa Oya,Guang-Nan Luo他9名
[151]. Development of tritium recovery by flowing O2+Ar gases at steam generator in fast breeder reactor
FUSION SCIENCE AND TECHNOLOGY 60/ 1423-1426 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Takuji Oda,Satoru Tanaka,Kenji Okuno
[152]. Development of Monte Carlo Simulation Code to Model Behavior of Hydrogen Isotopes Loaded into Tungsten Containing Vacancies
FUSION SCIENCE AND TECHNOLOGY 60/ 1455-1458 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Takuji Oda [共著者]M. Shimada,K. Zhang,P. Calderoni,Y. Oya,M. Sokolov,R. Kolasinski,J. P. Sharpe,,Y. Hatano
[153]. Dynamics of hydrogen isotope trapping and detrapping for tungsten under simultaneous triple ion (C+, D2+ and He+) implantation
JOURNAL OF NUCLEAR MATERIALS 415/ S701-S704 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Makoto Kobayashi,Rie Kurata,Wangjing Wang,Naoko Ashikawa,Akio Sagara,Naoaki Yoshida,Yuji Hatano,Kenji Okuno
[154]. Retention behaviors of hydrogen isotope in boron film exposed to H-H discharge in LHD
JOURNAL OF NUCLEAR MATERIALS 415/ S728-S730 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Masato Suzuki [共著者]Rie Kurata,Makoto Kobayashi,Naoko Ashikawa,Akio Sagara,Yasuhisa Oya,Kenji Okuno
[155]. Impurity effects on hydrogen isotope retention in carbon-oxygen containing boron films
FUSION SCIENCE AND TECHNOLOGY 60/1 412-416 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Katsushi Matsuoka [共著者]Makoto Kobayashi,Rie Kurata,Junya Osuo,Naoko Ashikawa,Akio Sagara,Yasuhisa Oya,Kenji Okuno
[156]. Study on annihilation behavior of γ-ray induced defects in Li2O
JOURNAL OF NUCLEAR MATERIALS 417/ 700-702 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Makoto Kobayashi [共著者]Sachiko Suzuki,Rie Kurata,Wanjing Wang,Toshiyuki Fujii,Hajimu Yamana,Kaiming Feng,Yasuhisa Oya,Kenji Okuno
[157]. Fluence dependence of deuterium retention in oxidized SS-316
JOURNAL OF NUCLEAR MATERIALS 417/ 1154-1157 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Sachiko Suzuki,Masao Matsuyama,Takumi Hayashi,Toshihiko Yamanishi,Yamato Asakura,Kenji Okuno
[158]. Trapping and Depth Profile of Tritium in Surface Layers of Metallic Materials
JOURNAL OF NUCLEAR MATERIALS 417/ 900-903 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]M. Matsuyama [共著者]Z. Chen,K. Nisimura,S. Akamaru,Y. Torikai,Y. Hatano,N. Ashikawa,Y. Oya,K. Okuno,T. Hino
[159]. Temperature dependence of retention of energetic deuterium and carbon simultaneously implanted into tungsten
JOURNAL OF NUCLEAR MATERIALS 417/ 555-558 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Wanjing Wang [共著者]Makoto Kobayashi,Rie Kurata,Naoko Ashikawa,Akio Sagara,Naoaki Yoshida,Guang-Nan Luo,Yasuhisa Oya,Kenji Okuno
[160]. Chemical States and Deuterium retention behavior of vacuum plasma sprayed tungsten coatings
JOURNAL OF NUCLEAR MATERIALS 417/ 551-554 (2011年)
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yaran Niu [共著者]Sachiko Suzuki,Xuebin Zheng,Chuanxian Ding,Junling Chen,Yasuhisa Oya,Kenji Okuno
[161]. Surface analysis of VPS-W coatings boronized by an ICRF discharge in HT-7
JOURNAL OF NUCLEAR MATERIALS 417/ 900-903 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Zhongshi Yang [共著者]Wanjing Wang,Kenji Okuno,Yasuhisa Oya,Guang-Nan Luo
[162]. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility
JOURNAL OF NUCLEAR MATERIALS 417/ 1336-1340 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]P. Calderoni [共著者]J. Sharpe,M. Shimada,B. Denny,B. Pawelko,S. Schuetz,G. Longhurst,Y. Hatano,M. Hara,Y. Oya,T. Otsuka,K. Katayama,S. Konishi,K. Noborio,Y. Yamamoto
[163]. Dynamic behaviors of deuterium retained in SS-316 oxidized at various temperatures
FUSION SCIENCE AND TECHNOLOGY 60/1 403-406 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Makoto Kobayashi [共著者]Wanjing Wang,Rie Kurata,Masao Matsuyama,Takumi Hayashi,Toshihiko Yamanishi,Yamato Asakura,Yasuhisa Oya,Kenji Okuno
[164]. Role of energetic tritium chemistry on developing thermonuclear fusion reactors
FUSION ENGINEERING AND DESIGN 86/ 2358-2361 (2011年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Kenji Okuno [共著者]Yasuhisa Oya,Rie Kurata,Makoto Kobayashi
[165]. Elucidation of Annihilation Processes of Defects Induced by g-irradiation in Li2TiO3
FUSION ENGINEERING AND DESIGN 85/ 2331-2333 (2010年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Sachiko Suzuki [共著者]Makoto Kobayashi,Rie Kurata,Wanjing Wang,Toshiyuki Fujii,Hajimu Yamana,Kaiming Feng,Yasuhisa Oya,Kenji Okuno
[166]. Crystal structure change of Li2+xTiO3+y tritium breeder under moist air
JOURNAL OF NUCLEAR MATERIALS 404/ 217-221 (2010年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Masanori Hara [共著者]Yuka Togashi,Masao Matsuyama,Yasuhisa Oya,Kenji Okuno
[167]. Retention Behavior of Hydrogen Isotopes in Boron Film Deposited on SS-316 for LHD first wall
FUSION ENGINEERING AND DESIGN 85/ 2328-2330 (2010年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Kenji Okuno [共著者]Sachiko Suzuki,Makoto Kobayashi,Rie Kurata,Matsuyama Masao,Naoko Ashikawa,Akio Sagara,Yasuhisa Oya
[168]. Correlation between deuterium retention and microstructure change for tungsten under triple ion implantation
PHYSICA SCRIPTA T138/ 014051 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Sachiko Suzuki,Wanjing Wang,Rie Kurata,Makoto Kobayashi,Naoko Ashikawa,Akio Sagara,Naoaki Yoshida,Kenji Okuno
[169]. Trapping behaviour of deuterium ions implanted into tungsten simultaneously with carbon ions
PHYSICA SCRIPTA T138/ 014050 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Makoto Kobayashi [共著者]Sachiko Suzuki,Wanjing Wang,Rie Kurata,Katsuya Kida,Naoko Ashikawa,Akio Sagara,Naoaki Yoshida,Yasuhisa Oya,Kenji Okuno
[170]. Design of gaseous tritium recovery system applying commercially available membrane-type dehumidifier
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 46/ 614-647 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yamato Asakura [共著者]Masahiro Tanaka,Tatsuhiko Uda,Hideki Ogawa,Shigeyuki Takami,Yasuhisa Oya,Kenji Okuno,Satoshi Fukada
[171]. Behavior of hydrogen isotope retention in carbon implanted tungsten
JOURNAL OF NUCLEAR MATERIALS 390-391/ 622-625 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Yuji Inagaki,Sachiko Suzuki,Hirotada Ishikawa,Yohei Kikuchi,Akira Yoshikawa,Tomohiro Iwakiri,Naoko Ashikawa,Akio Sagara,Naoaki Yoshida,Kenji Okuno
[172]. Influence of carbon concentration on chemical behavior of energetic deuterium implanted into carbon-contained boron films
JOURNAL OF NUCLEAR MATERIALS 390-391/ 200-202 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Sachiko Suzuki [共著者]Yu Yang,Akira Yoshikawa,Yohei Kikuchi,Yasuhisa Oya,Kenji Okuno
[173]. Chemical behavior of hydrogen isotopes into boronized film in LHD
JOURNAL OF NUCLEAR MATERIALS 386-388/ 367-370 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Akira Yoshikawa [共著者]Hideo Miyauchi,Toshihiko Nakahata,Taichi Suda,Naoko Ashikawa,Akio Sagara,Nobuaki Noda,Yasuhisa Oya,Kenji Okuno
[174]. Study on retention behavior and chemical states of energetic deuterium implanted into carbon-contained boron film
JOURNAL OF NUCLEAR MATERIALS 386-388/ 371-374 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yohei Kikuchi [共著者]Yu Yang,Akira Yoshikawa,Taichi Suda,Hideo Miyauchi,Toshihiko Nakahata,Akio Sagara,Nobuaki Noda,Yasuhisa Oya,Kenji Okuno
[175]. Role of lithium on chemical states and retention behavior of tritium in Li2TiO3
FUSION SCIENCE AND TECHNOLOGY 56/ 821-825 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yuji Inagaki [共著者]Haibo Liu,Hirotada Ishikawa,Sachiko Suzuki,Akira Yoshikawa,Kaiming Feng,Yasuhisa Oya,Kenji Okuno
[176]. Temperature dependence of oxide layer formation on hydrogen isotope retention in type 316 stainless steel
FUSION SCIENCE AND TECHNOLOGY 56/ 799-803 (2009年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Kenji Okuno [共著者]Hirotada Ishikawa,Yasuhisa Oya,Takumi Hayashi,Toshihiko Yamanishi
[177]. Application of membrane dehumidifier for gaseous tritium recovery in LHD
FUSION SCIENCE AND TECHNOLOGY 54/ 75-78 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Asakura [共著者]M. Tanaka,T. Uda,H. Ogawa,S. Takami,Y. Oya,K. Okuno
[178]. IR observation on O–D vibration in LiNbO3 and LiTaO3 single crystal irradiated by 3 keV D2
JOURNAL OF NUCLEAR MATERIALS 382/ 46-50 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Tianyong Luo [共著者]Takuji Oda,Yasuhisa Oya,Satoru Tanaka
[179]. Measurement of tritium permeation in flibe (2LiF-BeF2)
FUSION ENGINEERING AND DESIGN 83/ 1331-1334 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]P. Calderoni [共著者]P. Sharpe,M. Hara,Y. Oya
[180]. Detrapping behavior of tritium trapped via hot atom chemical process in neutron-irradiated ternary lithium oxides
JOURNAL OF NUCLEAR MATERIALS 375/ 1-7 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Makoto Oyaidzu [共著者]Yusuke Nishikawa,Taichi Suda,Takashi Shinozaki,Akira Yoshikawa,Yasuhisa Oya,Kenzo Munakata,Hajimu Yamana,Kenji Okuno
[181]. Existence states of deuterium irradiated into LiAlO2
JOURNAL OF NUCLEAR MATERIALS 372/ 53-58 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Tianyong Luo [共著者]Takuji Oda,Yasuhisa Oya,Satoru Tanaka
[182]. Oxidation behavior of SiC/SiC composites for helium cooled solid breeder blanket
FUSION ENGINEERING AND DESIGN 83/ 1490-1494 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]S. Nogami [共著者]N. Otake,A. Hasegawa,Y. Katoh,A. Yoshikawa,M. Satou,Y. Oya,K. Okuno
[183]. Inhibition of Lipid peroxidation induced by tritiated water due to Tea Catechins
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY 275/ 483-486 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Masayo Kubota [共著者]Hiroyuki Haga,Yasuhisa Oya,Kenji Okuno
[184]. Study on interaction between tritium behavior and thermal annihilation behavior of 14 MeV neutron-irradiated Li4SiO4
FUSION SCIENCE AND TECHNOLOGY 54/ 127-130 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]H. Ishikawa [共著者]T. Suda,Y. Nishikawa,M. Oyaidzu,T. Shinozaki,T. Fujii,K. Takakura,K. Ochiai,K. Munakata,H. Yamana,Y. Oya,K. Okuno
[185]. Recovery of tritium dissolved in sodium at the steam generator of fast breeder reactor
FUSION SCIENCE AND TECHNOLOGY 54/ 337-340 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Takuji Oda,Satoru Tanaka,Kenji Okuno
[186]. Monte Carlo simulation on tritium permeation through steels
FUSION SCIENCE AND TECHNOLOGY 54/ 537-540 (2008年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Takuji Oda [共著者]Yasuhisa Oya,Kenji Okuno,Satoru Tanaka
[187]. Hydrogen isotope behavior and its interaction with post irradiated energetic helium in SiC
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY 272/ 639-644 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Onishi,H. Miyauchi,K. Okuno,S. Tanaka
[188]. Hydrogen isotopes retention in JT-60U
JOURNAL OF NUCLEAR MATERIALS 363-365/ 854-861 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Hirohata [共著者]T. Tanabe,Y. Oya,K. Okuno,K. Masaki,N. Miya
[189]. Effects of helium implantation on hydrogen isotope retention behavior in SiC
JOURNAL OF NUCLEAR MATERIALS 363-365/ 933-937 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Hideo Miyauchi,Taichi Suda,Yusuke Nishikawa,Takuji Oda,Kenji Okuno,Satoru Tanaka
[190]. Comparison of boronized wall in LHD and JT-60U
JOURNAL OF NUCLEAR MATERIALS 363-365/ 1352-1357 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]N. Ashikawa [共著者]K. Kizu,J. Yagyu,Y. Nobuta,T. Nakahata,K. Nishimura,A. Yoshikawa,Y. Ishimoto,Y. Oya,K. Okuno,N. Miya,T. Hino,S. Masuzaki,A. Sagara,N. Ohyabu
[191]. Ion fluence dependence on chemical behavior of energetic deuterium implanted into oxygen-contained boron film
JOURNAL OF NUCLEAR MATERIALS 363-365/ 925-928 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]H. Miyauchi [共著者]A. Yoshikawa,M. Oyaidzu,Y. Oya,A. Sagara,N. Noda,K. Okuno
[192]. Effect of oxygen concentration on the chemical behavior of deuterium implanted into oxygen-containing boron thin film
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1527-1530 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Akira Yoshikawa [共著者]Makoto Oyaidzu,Hideo Miyauchi,Yasuhisa Oya,Akio Sagara,Nobuaki Noda,Kenji Okuno
[193]. Dependence of implantation temperature on chemical behavior of energetic deuterium implanted into tungsten carbide
JOURNAL OF NUCLEAR MATERIALS 363-365/ 910-914 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]E. Igarashi [共著者]Y. Nishikawa,T. Nakahata,A. Yoshikawa,M. Oyaidzu,Y. Oya,K. Okuno
[194]. Reaction rate of beryllium with fluorine Ion for Flibe redox control
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1190-1196 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]S. Fukada [共著者]G.R. Smolik,M. Simpson,R.A. Anderl,J.P. Sharpe,Y. Oya,Y. Hatano,T. Terai,K. Okuno,D.-K. Sze,D. Petti,A. Sagara
[195]. Effects of chemical status of carbon on deuterium retention in carbon containing materials
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1522-1526 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Makoto Oyaidzu [共著者]Hiromi Kimura,Toshihiko Nakahata,Hideo Miyauchi,Masayuki Tokitani,Yasuhisa Oya,Hirotomo Iwakiri,Naoaki Yoshida,Kenji Okuno
[196]. Dynamics of deuterium implanted in boron coating film for wall conditioning
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1170-1174 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Toshihiko Nakahata [共著者]Akira Yoshikawa,Makoto Oyaidzu,Yasuhisa Oya,Yuki Ishimoto,Kaname Kizu,Naoko Ashikawa,Kiyohiko Nishimura,Naoyuki Miya,Kenji Okuno
[197]. Behavior of deuterium in boron films covered by oxygen-containing layer
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1503-1506 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]M. X. Wang [共著者]H. Miyauchi,T. Nakahata,Y. Nishikawa,Y. Oya,N. Noda,K. Okuno
[198]. Validation of potential models for Li2O in classical molecular dynamics simulation", Journal of Nuclear Materials
JOURNAL OF NUCLEAR MATERIALS 367-370/ 263-268 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Takuji Oda [共著者]Yasuhisa Oya,Satoru Tanaka,William J. Weber
[199]. Distribution of hydrogen isotope retained in the divertor tiles used in JT-60U
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1260-1265 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Hirohata [共著者]T. Tanabe,T. Shibahara,M. Oyaidzu,K. Sugiyama,Y. Oya,A. Yoshikawa,Y. Onishi,T. Arai,K. Masaki,Y. Ishimoto,K. Okuno,N. Miya
[200]. Hydrogen isotope behavior in the first wall of JT-60U after deuterium plasma operation
JOURNAL OF NUCLEAR MATERIALS 367-370/ 1266-1270 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Hirohata,M. Oyaidzu,T. Shibahara,K. Sugiyama,A. Yoshikawa,Y. Onishi,Y. Ishimoto,J. Yagyu,T. Arai,K. Masaki,K. Okuno,N. Miya,S. Tanaka,T. Tanabe
[201]. Hydrogen retention and carbon deposition in plasma facing components and shadowed area of JT-60U
NUCLEAR FUSION 47/ 1577-1582 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]K. Masaki [共著者]T. Tanabe,Y. Hirohata,Y. Oya,T. Shibahara,T. Hayashi,K. Sugiyama,T. Arai,K. Okuno,N. Miya
[202]. Effects of implantation conditions on retention behavior of deuterium in highly oriented pyloritic graphite
FUSION SCIENCE AND TECHNOLOGY 82/ 1762-1766 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]T. Suda [共著者]H. Miyauchi,A. Yoshikawa,H. Kimura,Y. Oya,K. Okuno
[203]. Temperature dependence on hydrogen isotope behaviors in pure SiC and helium ion implanted SiC
FUSION SCIENCE AND TECHNOLOGY 82/ 2582-2587 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]H. Miyauchi,T. Suda,A. Yoshikawa,K. Okuno,S. Tanaka
[204]. Study for the behavior of tritiated water vapor on organic materials
FUSION SCIENCE AND TECHNOLOGY 52/ 696-700 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]K. Kobayashi [共著者]T. Hayashi,T. Yamanishi,Y. Oya,K. Okuno
[205]. Hydrogen isotope retentions and erosion/deposition profiles in the first wall of JT-60U
FUSION SCIENCE AND TECHNOLOGY 52/ 554-558 (2007年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Hirohata,T. Nakahata,T. Suda,M. Yoshida,T. Arai,K. Masaki,K. Okuno,T. Tanabe
[206]. JT-60UにおけるW型ダイバータタイル中の水素および重水素蓄積挙動と損耗・再堆積分布(解説)
プラズマ・核融合学会誌 82/ 226-232 (2006年)
[責任著者・共著者の別] 共著者
[著者] [責任著者]大矢恭久 [共著者]広畑優子,田辺哲朗,奥野健二,宮直之,田中知
[207]. 熱脱離による水素同位体の除去(解説)
真空 49/ 56-61 (2006年)
[責任著者・共著者の別] 責任著者
[著者] 大矢恭久
[208]. Hydrogen retention and depth profile in divertor tiles of JT-60 exposed to hydrogen discharges
FUSION ENGINEERING AND DESIGN 81/ 289-294 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]A. Yoshikawa [共著者]Y. Hirohata,Y. Oya,T. Shibahara,M. Oyaidzu,T. Arai,Y. Gotoh,K. Masaki,N. Miya,K. Okuno,T. Tanabe
[209]. Quantitative Measurement of beryllium-controlled Redox of hydrogen fluoride in molten FLiBe
FUSION ENGINEERING AND DESIGN 81/ 541-547 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Michael F. Simpson [共著者]Galen R. Smolik,John P. Sharpe,Robert A. Anderl,David A. Petti,Yuji Hatano,Masanori Hara,Yasuhisa Oya,Satoshi Fukada,Saturu Tanaka,Takayuki Terai,Dai-Kai Sze
[210]. Interaction between hydrogen isotopes and damaged structures produced by He+ implantation in SiC
FUSION ENGINEERING AND DESIGN 81/ 987-992 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Onishi,T. Takeda,H. Kimura,K. Okuno,S. Tanaka
[211]. Chemical behavior of energetic deuterium implanted into tungsten carbide
FUSION ENGINEERING AND DESIGN 81/ 295-299 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]H. Kimura [共著者]Y. Nishikawa,T. Nakahata,M. Oyaidzu,Y. Oya,K. Okuno
[212]. Sorption and desorption of tritiated water on four kinds of materials for ITER
FUSION ENGINEERING AND DESIGN 81/ 1379-1384 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]K. Kobayashi [共著者]T. Hayashi,M. Nishi,Y. Oya,K. Okuno
[213]. Helium irradiation effects for deuterium retention in boron coating films
FUSION ENGINEERING AND DESIGN 81/ 301-306 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]T. Takeda [共著者]A. Yoshikawa,M. Oyaidzu,T. Nakahata,Y. Nishikawa,H. Kimura,Y. Onishi,H. Miyauchi,Y. Oya,A. Sagara,N. Noda,K. Okuno
[214]. Reactivity of H2O gas with the surface of polycrystalline Li2O pellet
FUSION ENGINEERING AND DESIGN 81/ 613-618 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Takuji Oda [共著者]Yasuhisa Oya,Ryan Uy Olivares,Satoru Tanaka
[215]. JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments
FUSION ENGINEERING AND DESIGN 81/ 1439-1449 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]David A. Petti [共著者]G.R. Smolik,Michael F. Simpson,John P. Sharpe,R.A. Anderl,S. Fukada,Y. Hatano,M. Hara,Y. Oya,T. Terai,D.-K. Sze,S. Tanaka
[216]. Emission of methane from stainless steel surface investigated by using tritium as a radioactive tracer
CHEMISTRY LETTERS 35/ 292-293 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Shogo Higaki [共著者]Yasuhisa Oya,Yoshihiro Makide
[217]. Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges
JOURNAL OF NUCLEAR MATERIALS 357/ 115-125 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]T. Shibahara [共著者]T. Tanabe,Y. Hirohata,Y. Oya,M. Oyaidzu,A. Yoshikawa,Y. Onishi,T.Arai,K. Masaki,K. Okuno,N. Miya
[218]. Hydrogen retention of JT-60 open divertor tiles exposed to HH discharges
NUCLEAR FUSION 46/ 841-847 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]T. Shibahara [共著者]T. Tanabe,Y. Hirohata,Y. Oya,M. Oyaidzu,A. Yoshikawa,Y. Onishi,T. Arai,K. Masaki,K. Okuno,N. Miya
[219]. Interactions between molten Flibe and metallic Be
FUSION ENGINEERING AND DESIGN 81/ 561-566 (2006年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]M. Hara [共著者]Y. Hatano,M. Simpson,G. Smolik,P. Sharp,Y. Oya,S. Tanaka,K. Okuno,M. Nishikawa,T. Terai,R. Anderl,D. Petti
[220]. Dynamic hydrogen isotope behavior and its chemical states in SiC by XPS and TDS technique
JOURNAL OF NUCLEAR MATERIALS 337-339/ 595-599 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Onishi,H. Kodama,K. Okuno,S. Tanaka
[221]. Chemical reactions of atomic hydrogen at SiC surface and heterogeneous chemiluminescence
JOURNAL OF PHYSICS AND CHEMISTRY OF SOLIDS 66/ 513-520 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]V.V. Styrov [共著者]V.I. Tyutyunnikov,O.T. Sergeev,Y. Oya,K. Okuno
[222]. Hydrogen isotope distribution and retention in the inner divertor tile of JT-60U
FUSION ENGINEERING AND DESIGN 75-79/ 945-949 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Hirohata,Y. Shibahara,M. Oyaidzu,T. Arai,K. Masaki,Y. Gotoh,K. Okuno,N. Miya,T. Tanabe,T. Hino,S. Tanaka
[223]. Hydrogen retention in divertor tiles used in JT-60 for hydrogen discharge period", Journal of Nuclear Materials
JOURNAL OF NUCLEAR MATERIALS 337-339/ 609-613 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Hirohata [共著者]T. Shibahara,T. Tanabe,T. Arai,Y. Gotoh,Y. Oya,H. Yoshida,Y. Morimoto,J. Yagyu,K. Masaki,K. Okuno,T. Hino,N. Miya
[224]. Dynamic observation of the behavior of 3 keV D2+ irradiated into Li2O using IR absorption spectroscopy
JOURNAL OF NUCLEAR MATERIALS 346/ 306-311 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Takuji Oda [共著者]Yasuhisa Oya,Satoru Tanaka
[225]. Hydrogen isotope behavior in type 316 stainless steel sorbed by various methods
FUSION SCIENCE AND TECHNOLOGY 48/ 597-600 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Oya [共著者]Y. Onishi,H. Kodama,T. Kawano,Y. Asakura,T. Uda,K. Okuno,S. Tanaka
[226]. Retention of hydrogen isotopes in divertor tiles used in JT-60U
FUSION SCIENCE AND TECHNOLOGY 48/ 557-560 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Y. Hirohata [共著者]T. Shibahara,T. Tanabe,Y. Oya,T. Arai,Y. Gotoh,K. Masaki,J. Yagyu,M. Oyaidzu,K. Okuno,M. Nishikawa,N. Miya
[227]. FT-IR study on behavior of surface hydroxyls under irradiation of energetic particles
FUSION SCIENCE AND TECHNOLOGY 48/ 224-227 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]S. Tanaka [共著者]K. Chiba,Y. Oya
[228]. Preparation of pure boron coating film and its characterization by XPS and TDS
APPLIED SURFACE SCIENCE 244/ 240-243 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]M. Oyaidzu [共著者]A. Yoshikawa,H. Kodama,Y. Oya,A. Sagara,N. Noda,K. Okuno
[229]. Trapping and detrapping mechanism of deuterium in SiC studied by XPS and TDS techniques
MATERIALS TRANSACTIONS 46/ 552-556 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]Yasuhisa Oya [共著者]Yoshihiro Onishi,Kenji Okuno,Satoru Tanaka
[230]. Retention characteristics of hydrogen isotopes in JT-60U
JOURNAL OF NUCLEAR MATERIALS 337-339/ 553-559 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]K. Masaki [共著者]K. Sugiyama,T. Hayashi,K. Ochiai,Y. Gotoh,T. Shibahara,Y. Hirohata,Y. Oya,N. Miya,T. Tanabe
[231]. Helium irradiation effects on retention behavior of deuterium implanted into boron coating film by PCVD
JOURNAL OF NUCLEAR MATERIALS 337-339/ 649-653 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]H. Kodama [共著者]M. Oyaidzu,A. Yoshikawa,H. Kimura,Y. Oya,M. Matsuyama,A. Sagara,N. Noda,,K. Okuno
[232]. Hydrogen isotopes behavior on Li2TiO3 under varied surface condition
FUSION ENGINEERING AND DESIGN 75-79/ 765-768 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]R. Olivares [共著者]T. Oda,Y. Oya,K. Tsuchiya,S. Tanaka
[233]. Thermal desorption behavior of hydrogen isotopes interacting with radiation defects in Li2O
FUSION ENGINEERING AND DESIGN 75-79/ 835-839 (2005年) [査読] 有
[責任著者・共著者の別] 共著者
[著者] [責任著者]T. Oda [共著者]Y. Oya,S. Tanaka