Rchr
J-GLOBAL ID:202101007241618496
Update date: May. 15, 2024
Tokitani Masayuki
トキタニ マサユキ | Tokitani Masayuki
Affiliation and department:
Research theme for competitive and other funds (15):
- 2020 - 2024 Development of the W/ODS-Cu divertor heat removal component by using the Advanced Multi-Step Brazing (AMSB)
- 2020 - 2023 Clarification of Damage Process by Fusion Plasma in High Toughness Tungsten Alloys
- 2017 - 2020 Properties of Beryllium for Plasma Facing Material in Fusion Reactor
- 2017 - 2020 Development of the W/ODS-Cu divertor heat removal component by using the Advanced Brazing Technique
- 2016 - 2019 Is it possible to apply a liquid metal jet flowing at a velocity similar to a tap water flow as a heat receiving device that can withstand the ultra-high heat load in the fusion reactor?
- 2014 - 2019 Hydrogen retention in radiation-damaged tungsten and development of retention reduction method
- 2015 - 2018 Effect of plasma transport in the stochastic magnetic field lines layer on the divertor heat and particle load profiles
- 2014 - 2017 Study on dynamics of W melt-layer splashing generated by a transient heat load simulator with a plasma gun in an external magnetic field
- 2014 - 2017 Effects of the surface morphologies on the plasma facing materials during the long pulse discharge in the large-sized plasma confinement devices
- 2013 - 2016 Development and optimization of in-situ diagnostics methods for plasma facing materials
- 2011 - 2013 Study of the directionality on the redeposition layer in fusion devices
- 2011 - 2013 Microstructural characterization of the Mixed-material deposition layer by using the advanced nano-fabrication technique
- 2008 - 2010 Evaluation of the microstructure and retention properties of plasma particles on mix-material deposition layer
- 2005 - 2006 大型プラズマ閉じ込め装置における材料の損耗・損傷過程に関する研究
- 2004 - 2004 Study on Damage of Plasma Facing Materials by He Irradiation and its Diagnostic
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Papers (223):
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Fanwei Yu, Takuma Tomizawa, Noritaka Yusa, Masayuki Tokitani. Signal-distribution-based crack detection for divertor monoblock inspection using eddy current testing. Fusion Engineering and Design. 2024. 203. 114404-114404
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D. Nishijima, M. Tokitani, D. Nagata, T. Schwarz-Selinger, A. Založnik, F. Chang, R.P. Doerner, M.I. Patino, M.J. Simmonds, M.J. Baldwin, et al. Reply to Comment on ‘Deuterium supersaturated surface layer in tungsten: ion energy dependence’. Nuclear Fusion. 2024. 64. 6. 068002-068002
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Shuangyuan Feng, Shin Kajita, Ryo Yasuhara, Masayuki Tokitani, Quan Shi. Formation of corrugated nano-fuzz tungsten thin film on silicon via helium plasma irradiation. Japanese Journal of Applied Physics. 2023. 63. 1. 010904-010904
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Y. Torikai, G. Kikuchi, A. Owada, S. Masuzaki, T. Otsuka, N. Ashikawa, M. Yajima, M. Tokitani, Y. Oya, S.E. Lee, et al. Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall. Nuclear Fusion. 2023. 64. 1. 016032-016032
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D. Nishijima, M. Tokitani, D. Nagata, T. Schwarz-Selinger, A. Založnik, F. Chang, R.P. Doerner, M.I. Patino, M.J. Simmonds, M.J. Baldwin, et al. Deuterium supersaturated surface layer in tungsten: ion energy dependence. Nuclear Fusion. 2023. 63. 12. 126003-126003
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MISC (40):
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増崎貴, 増崎貴, 矢嶋美幸, 矢嶋美幸, 田中将裕, ZHAO Minghong, 本島厳, 本島厳, 森崎友宏, 森崎友宏, et al. Tritium retention in the first-wall and divertor tiles during the deuterium plasma campaigns in LHD. 日本原子力学会秋の大会予稿集(CD-ROM). 2023. 2023
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矢嶋美幸, 吉田直亮, 増崎貴, 時谷政行, 大塚哲平, 本島厳. Investigation of Hydrogen Isotope Retention on the Fist Wall after Deuterium Experiment in LHD. プラズマ・核融合学会年会(Web). 2020. 37th
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E. Joffrin, S. Abduallev, M. Abhangi, P. Abreu, V. Afanasev, M. Afzal, K. M. Aggarwal, T. Ahlgren, L. Aho-Mantila, N. Aiba, et al. Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall. Nuclear Fusion. 2019. 59. 11
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時谷政行, 宮本光貴, 増崎貴, 波多野雄治, 大矢恭久, 大塚哲平, 濱口大, 黒滝宏紀, 小柳津誠, 鈴木卓美, et al. JET-ILW実験で使用されたWダイバータタイルおよびBeリミタタイルの微細構造. プラズマ・核融合学会年会(Web). 2019. 36th
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本島厳, 本島厳, 矢嶋美幸, 吉田直亮, 増崎貴, 坂本隆一, 坂本隆一, 時谷政行, 時谷政行, 田中宏彦, et al. Evaluation of fuel helium retention distribution on the first wall in LHD. プラズマ・核融合学会年会(Web). 2016. 33rd
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Patents (3):
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Brazing method for copper and copper alloy
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Brazing method for alumina dispersion strengthened copper
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Brazing method for alumina dispersion strengthened copper
Awards (8):
- 2022/05 - Japan Welding Society Japan Welding Society Technical Commission on Solid Phase Welding and Brazing Award 2021 Advanced brazing technique for copper and copper alloy
- 2021/07 - National Institutes for Quantum and Radiological Science and Technology Outstanding Awards on the Fusion Engineering Collaborative Research Study of tritium retention properties on the plasma facing component and dust particles in the JET ILW experiment
- 2019/07 - National Institutes of Natural Sciences 8th Young Researcher Award on National Institute of Natural Sciences
- 2019/05 - The 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17) Poster Prize
- 2017/02 - Fusion Energy Forum of Japan 2016 Masaji Yoshikawa Prize for Fusion Energy
- 2015/09 - Atomic Energy Society of Japan 12th Fusion Engineering Division Prize
- 2012/11 - The Japan Society of Plasma Science and Nuclear Fusion Research 17th Academic Promotion Award
- 2010/06 - 8th Young Excellent Presentation Award
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