主要論文・解説記事

• ・N. Asakura, et al., “Studies of Power Exhaust and Divertor Design for a 1.5 GW-level Fusion Power DEMO”　appears in Nucl. Fusion (2017)
• ・N. Asakura, et al., “A Simulation Study of Large Power Handling in the Divertor for a Demo Reactor”, Nucl. Fusion, 53, 123013 (15pp) (2013)
• ・N. Asakura, et al., “Simulation study of power load with impurity seeding in advanced divertor, short super-X divertor, for a tokamak reactor”, J. Nucl. Mater., 463, 1238 (2015)
• ・N. Asakura, et al., “Investigation of Advanced Divertor Magnetic Configuration for DEMO Tokamak Reactor”, Transactions of Fusion Science and Technology, 63, 70-75 (2013)
• ・N. Asakura, et al., “Investigation of Carbon Dust Accumulation in the JT-60U Tokamak Vacuum Vessel”, J. Nucl. Mater., 438 (2013) S659–S663
• ・N. Asakura, et al., “Investigations of Impurity Seeding and Radiation Control for Long-pulse and High-density H-mode Plasmas in JT-60U”, Nucl. Fusion, 49, 115010 (8pp) (2009)
• ・N. Asakura, “Scrape-off Layer Plasma Flow in L- and H-Mode Plasmas on JT-60U”, Plasma and Fusion Res., 4, 021-1 (2009)
• ・N.Asakura and ITPA SOL and Divertor Physics Topical Group, “Understanding of the SOL Plasma Flow in Tokamaks, and Influence on the Plasma Transport”, J. Nucl. Mater., 363–365, 41-51 (2007)
• ・N. Asakura, et al., “Fast Measurement of ELM Heat and Particle Fluxes, and Plasma Flow in the Scrape-off Layer of the JT-60U Tokamak”, Plasma Phys. Control. Fusion, 44, A313-A321 (2002)
• ・N. Asakura, et al., “Measurement of Natural Plasma Flow along the Field Lines in the Scrape-Off Layer on the JT-60U Divertor Tokamak” Phys. Rev. Lett., 84, 3093-3096 (2000)
• ・N. Asakura, et al., “Heat and Particle Transport of SOL and Divertor Plasmas in the W-shaped Divertor on JT-60U”, Nucl. Fusion, 39, 1983-1994 (1999)
• ・N. Asakura, et al., “Degradation of Energy and Particle Confinement in High Density ELMy H-mode Plasmas on JT-60U”, Plasma Phys. Control. Fusion, 39, 1295-1314 (1997)
• ・N. Asakura, et al., “Field Reversal Effects on Divertor Plasmas under Radiative and Detached Conditions in JT-60U”, Nucl. Fusion, 36, 795-813 (1996)
• ・朝倉伸幸、他、「日本における原型炉ダイバータ概念の現状と開発課題」「ITER 及び原型炉ダイバータ工学の現状と研究開発」, Plasma Fusion Res. 92, 870-876 and 886-890 (2016)
• ・朝倉伸幸、他、「トカマク実験におけるタングステンの輸送および制御研究の進展」、J. Plasma Fusion Res. 87, 577-590 (2011).
• ・朝倉伸幸、他、「トカマク実験におけるタングステンの輸送および制御研究の進展」、J. Plasma Fusion Res. 87, 577-590 (2011).
• ・朝倉伸幸、「トカマク・ダイバータとスクレイプ・オフ層における高速プラズマ流」、J. Plasma Fusion Res. 83, 501-508 (2007).
• ・朝倉伸幸、「トカマクにおけるスクレイプオフ層とダイバータプラズマ研究の進展」、J. Plasma Fusion Res. 80, 190-200 (2004)
• ・朝倉伸幸、「3.9.3ダイバータプラズマ」、原子力・量子・核融合辞典　第一分冊　原子核物理とプラズマ物理・核融合､丸善出版、工藤和彦　編集員会、I-190-191　(2014)　

所属学会

• プラズマ・核融合学会、日本物理学会、アメリカ物理学会
• 関連URL： http://www.fusion.qst.go.jp/rokkasyo/index.html

主要論文

• ・N. Umeda, E. Kashiwagi, H. Tobari, Y. Kojima, M. Dairaku, M. Hanada, T. Maeshima, K. Watanabe, H. Yamanaka: Development of ultra-high voltage insulation technology for the power supply components in neutral beam system on ITER, 26th IAEA Fusion Energy Conference, FIP/P4-10, Kyoto, (2017)

主要論文

核融合原型炉関連

• ・Y. Sakamoto et al., “DEMO Concept Development and Assessment of Relevant Technologies”, 25th IAEA Int. Conf. on Fusion Energy (St. Petersburg, Russia, 2014) FIP/3-4Rb.
• ・Y. Sakamoto et al., “Relationship between net electric power and radial build of DEMO based on ITER steady-state scenario parameters”, Fusion Eng. Des. 89, 2440- 2445 (2014)
• ・Y. Sakamoto et al., “Present Status of Integrated Performance Achieved in Tokamak Experiments and Critical Issues Towards DEMO Reactor”, J. Plasma Fusion Res. SERIES 9 375 (2010)
• ・「核融合発電の可能性」、電気計算2015年11月 ・特集「テキスト核融合炉（第４章、他）」、プラズマ・核融合学会誌2011年2月

プラズマ物理・トカマク実験関連

• ・Y. Sakamoto et al., “Development of reversed shear plasmas with high bootstrap current fraction towards reactor relevant regime in JT-60U”, Nucl. Fusion 49, 095017 (2009)
• ・Y. Sakamoto et al., “Response of Toroidal Rotation Velocity to Electron Cyclotron Wave Injection in JT-60U”, Plasma Phys. Control. Fusion 48, A63-A70 (2006)
• ・Y. Sakamoto et al., “Stationary High Confinement Plasmas with Large Bootstrap Current Fraction in JT-60U”, Nucl. Fusion 45, 574-580 (2005)
• ・Y. Sakamoto et al., “Characteristics of Internal Transport Barriers in JT-60U Reversed Shear Plasmas”, Nucl. Fusion 41, 865-872 (2001)
• ・小特集「炉心プラズマの定常化に向けたトーラス・プラズマ研究開発の現状と展望（3.2節）」、プラズマ・核融合学会誌2007年5月
• ・小特集「燃焼・高ベータプラズマの実現に向けたプラズマ分布制御の課題（３章）」、プラズマ・核融合学会誌2010年9月

主要論文

核融合原型炉関連

• ・Y. Sakamoto et al., “DEMO Concept Development and Assessment of Relevant Technologies”, 25th IAEA Int. Conf. on Fusion Energy (St. Petersburg, Russia, 2014) FIP/3-4Rb.
• ・Y. Sakamoto et al., “Relationship between net electric power and radial build of DEMO based on ITER steady-state scenario parameters”, Fusion Eng. Des. 89, 2440- 2445 (2014)
• ・Y. Sakamoto et al., “Present Status of Integrated Performance Achieved in Tokamak Experiments and Critical Issues Towards DEMO Reactor”, J. Plasma Fusion Res. SERIES 9 375 (2010)
• ・「核融合発電の可能性」、電気計算2015年11月 ・特集「テキスト核融合炉（第４章、他）」、プラズマ・核融合学会誌2011年2月

プラズマ物理・トカマク実験関連

• ・Y. Sakamoto et al., “Development of reversed shear plasmas with high bootstrap current fraction towards reactor relevant regime in JT-60U”, Nucl. Fusion 49, 095017 (2009)
• ・Y. Sakamoto et al., “Response of Toroidal Rotation Velocity to Electron Cyclotron Wave Injection in JT-60U”, Plasma Phys. Control. Fusion 48, A63-A70 (2006)
• ・Y. Sakamoto et al., “Stationary High Confinement Plasmas with Large Bootstrap Current Fraction in JT-60U”, Nucl. Fusion 45, 574-580 (2005)
• ・Y. Sakamoto et al., “Characteristics of Internal Transport Barriers in JT-60U Reversed Shear Plasmas”, Nucl. Fusion 41, 865-872 (2001)
• ・小特集「炉心プラズマの定常化に向けたトーラス・プラズマ研究開発の現状と展望（3.2節）」、プラズマ・核融合学会誌2007年5月
• ・小特集「燃焼・高ベータプラズマの実現に向けたプラズマ分布制御の課題（３章）」、プラズマ・核融合学会誌2010年9月

主要論文（研究系）

• ・Y. Someya et al., “Shutdown dose rate assessment during replacement of in-vessel components for a fusion DEMO reactor”, Fusion Eng. Des. 124, (2017), 615-618.
• ・Y. Someya et al., “Management Strategy for Radioactive Waste in the Fusion DEMO Reactor”, Fusion Sci. Technol. 68 (2015), 1282-1285.
• ・Y. Someya et al., “Design study of blanket structure based on a water-cooled solid breeder for DEMO”, Fusion Eng. Des. 98-99 (2015), 1872-1875.
• ・Y. Someya et al., “Estimation of TBR on the gap between neighboring blanket modules in the DEMO reactor”, Plasma Sci. Technol. 15-2, (2013) 171-174.
• ・Y. Someya et al., “Estimation of decay heat in fusion DEMO reactor”, Plasma and Fusion Research 7 (2012), 2405066.

受賞歴・表彰歴 ／ 特許等

• ・第29回プラズマ・核融合学会「若手学会発表賞」（2012）
• ・第11回日本原子力学会「核融合工学部会奨励賞」(2014)
• ・第19回プラズマ･核融合学会「学術奨励賞」(2014)
• ・第10回核融合エネルギーフォーラム「吉川允二核融合エネルギー奨励賞」(2016)

コメント（趣味等）

• ジグソーパズル、バスケットボール、スノーボード

主要論文

核融合原型炉関連

• ・Weixi Chen , Someya Yoji , Mitsuhiro Arikawa , Uto Hiroyasu , Hiwatari Ryoji , Umeda Naotaka , Kakudate Satoshi , Sakamoto Yoshiteru:　Development of poloidal horseshoe limiter concept for JA DEMOIEEE Transactions on Plasma Science, 50(11), 4233 - 4238, 2022-06, DOI:10.1109/TPS.2022.3176443

受賞歴・表彰歴 ／ 特許等

• ・第38回プラズマ・核融合学会「若手学会発表賞」（2021）

主要論文

核融合原型炉関連

• ・S. Tokunaga et al., “Multi-scale transport simulation of toroidal momentum source profile effect on internal transport barrier collapse”, Nucl. Fusion 49, 075023 (2009)
• ・S. Tokunaga et al., “A statistical analysis of avalanching heat transport in stationary enhanced core confinement regimes”, Phys. Plasmas 19, 092303 (2012)
• ・S. Tokunaga et al., “Conceptual design study of pellet fueling system for DEMO”, Fusion Eng. Des., In Press, (2017)

主要論文

核融合炉システム設計

• Ryoji HIWATARI, Youji SOMEYA, Hiroyasu UTOH, Yoshiteru SAKAMOTO, "Unlimited Fusion-Energy Station Based on Lithium Recovery from Seawater for a Net-Zero Carbon World", Plasma and Fusion Research 18, 1205077(2003)) https://doi.org/10.1585/pfr.18.1205077
• ・R. Hiwatari, Y. Asaoka, K. Okano, T. Yoshida and K.Tomabechi,　“Generation of Net Electric Power under the Foreseeable Physical and Engineering conditions”, Nuclear Fusion Vol.44, 2004, p106-116
• ・R.Hiwatari, K.Okano, Y.Asaoka, K. Shinya, and Y.Ogawa, “Demonstration tokamak fusion power plant for early realization of net electric power generation”, Nucl. Fusion Vol.45 No.2, 2005, p96-109.
• ・R.Hiwatari, K.Okano, Y.Asaoka, K.Tokimatsu, S.Konishi, Y.Ogawa, “Forthcoming Break-Even Conditions of Tokamak Plasma Performance for Fusion Energy Development” Journal of Plasma and Fusion Research Vol.81, No.11, 2005, p903-916
• ・R. Hiwatari, K. Okano, Y. Asaoka and Y. Ogawa, “Analysis of critical development issues towards advanced tokamak power plant CREST”, Nucl. Fusion Vol. 47, No.5, 2007, p387-394
• ・R.Hiwatari, K.Okano, Y.Ogawa, “Commissioning Scenario Without Initial Tritium Inventory for a Demonstration Reactor Demo-CREST”, Fusion Science and Technology 60, 2011, p1092-1095

炉心プラズマ設計

• ・R. Hiwatari, K. Okano, M. Ishida, K. Maeki, A. Hatayama, Y. Ogawa and M. Nakamura, “A control method of divertor plasma start-up assisted by tritium-ratio control for Demo-CREST”, Fusion Engineering and Design 86, 2011, p1099–1102
• ・R.Hiwatari, A.Hatayama, and T.Takizuka. “Effect of SOL Decay Length on Modeling of Divertor Detachment by Using Simple Core-SOL-Divertor Model”, Contrib. Plasma Phys. 48, 2008, p174-178

主要論文

不純物輸送&MCシミュレーション

• ・Y. Homma et al., “Kinetic modelling for neoclassical transport of high-Z impurity particles using a binary collision method”, Nuclear Fusion 56, 036009 (2016).
• ・Y. Homma et al., “Numerical modeling of the thermal force for the kinetic test-ion transport simulation based on the Fokker-Planck collision operator”, Contributions to Plasma Physics 54, No. 4-6, 394-398 (2014).
• ・Y. Homma et al., “Numerical modeling of the thermal force in a plasma for test-ion transport simulation based on a Monte Carlo Binary Collision Model (II) -- Thermal forces due to temperature gradients parallel and perpendicular to the magnetic field --”, Journal of Computational Physics, 250, 206-223 (2013).
• ・Y. Homma et al., “Numerical modeling of thermal force in a plasma for test-ion transport simulation based on Monte Carlo Binary Collision Model”, Journal of Computational Physics, 231, 3211-3227 (2012).

ダイバータ損耗研究

• • Y. Homma et al., “Numerical analysis of tungsten erosion and deposition processes under a DEMO divertor plasma and geometry”, Nuclear Materials and Energy, https://doi.org/10.1016/j.nme.2017.05.003

核融合炉第一壁熱負荷

核融合原型炉関連

• 核融合炉第一壁熱負荷
  ・Y. Miyoshi et al., “New model of plasma heat load on the first wall”, Fusion Eng. Design xxx (2017). (in press), doi: https://doi.org/10.1016/j.fusengdes.2017.04.068
• 核融合炉プラント設備
  ・Y. Miyoshi et al., “Optimized cooling water system design of Japan's DEMO”, Fusion Eng. Design (2017). (under submission)
• 核融合炉心制御
  ・Y. Miyoshi Y. Ogawa, “Multi-Input Multi-Output (MIMO) Control System with a State Equation for Fusion Reactors”, Plasma Fusion Res. 9, 1405015 (2014).
• ・Y. Miyoshi et al., “Research on Burn Control of Core Plasma with the Transport Code”, Plasma Fusion Res. 7, 2405135 (2012).
• 核融合炉設計
  ・Y. Miyoshi et al., “Optimization of the Poloidal Field Coil System by Using an Integrated Design Code for Tokamak Fusion Reactors”, JPFR-S. 9, pp. 186-189, (2010).