Paper

研究業績

Journal Paper

2024

  • S. Soma, M. Ishigaki, S. Abe, Y. Sibamoto, “Boundary layer measurements for validating CFD condensation model and analysis based on heat and mass transfer analogy in laminar flow condition,” Nuclear Engineering and Technology, 2024, https://doi.org/10.1016/j.net.2024.02.011
  • Y. Hirose, S. Abe, M. Ishigaki, Y. Sibamoto, T. Hibiki, “Simulation of a jet flow rectified by a grating-type structure using immersed boundary methods,” Progress in Nuclear Energy, Vol. 169, 105085, 2024, https://doi.org/10.1016/j.pnucene.2024.105085
  • S. Soma, M. Ishigaki, S. Abe, Y. Sibamoto, “Application of analytical wall functions to CFD analysis of condensation flow,” Nuclear Engineering and Design, Vol. 416, 112754, 2024, https://doi.org/10.1016/j.nucengdes.2023.112754

2022

  • M. Ishigaki, Y. Hirose, S. Abe, T. Nagai, T. Watanabe, “Estimation of Flow Field in Natural Convection with Density Stratification by Local Ensemble Transform Kalman Filter,” Fluids, Vol. 7, 237, 2022, https://doi.org/10.3390/fluids7070237
  • M. Ishigaki, S. Abe, A. Hamdani, Y. Hirose, “Numerical analysis of natural convection behavior in density stratification induced by external cooling of a containment vessel,” Annals of Nuclear Energy, Vol. 168, 108867, 2022, https://doi.org/10.1016/j.anucene.2021.108867
  • S. Abe, A. Hamdani, M. Ishigaki, Y. Sibamoto, “Experimental investigation of natural convection and gas mixing behaviors driven by outer surface cooling with and without density stratification consisting of an air-helium gas mixture in a large-scale enclosed vessel,” Annals of Nuclear Energy, Vol. 166, 108791, 2022 https://doi.org/10.1016/j.anucene.2021.108791
  • A. Hamdani, S. Abe, M. Ishigaki, Y. Sibamoto, T. Yonomoto, “CFD analysis on stratification dissolution and breakup of the air-helium gas mixture by natural convection in a large-scale enclosed vessel,” Progress in Nuclear Energy, Vol. 153, 104415, 2022, https://doi.org/10.1016/j.pnucene.2022.104415

2021

  • Kai Lu, Jinya Katsuyama, Koichi Masaki, Tadashi Watanabe and Yinsheng Li, “Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel,” J. Pressure Vessel Technol., 143(3): 031704 (2021) https://doi.org/10.1115/1.4049048
  • T. Watanabe, “Safety evaluation of nuclear power plant based on multiscale analyses,” Int. J. Multiphysics, 15, 169-184, (2021) https://doi.org/10.21152/1750-9548.15.2.169

2020

  • Tadashi Watanabe, “Transient shape variation and inner flow field of a rotating two-lobed liquid droplet,” Physical Review Fluids, 5 (2020) 083607 https://doi.org/10.1103/PhysRevFluids.5.083607
  • Yuki Koyano, Hiroyuki Kitahata, Koji Hasegawa, Satoshi Matsumoto, Katushiro Nishinari, Tadashi Watanabe, Akiko Kaneko, and Yutaka Abe, “Diffusion enhancement in a levitated droplet via oscillatory deformation,” Physical Review E, 102 033109(2020) https://doi.org/10.1103/PhysRevE.102.033109

2019

  • Tadashi Watanabe, “Numerical Simulation of Droplet Combustion using Volume-of-Fluid Method,” WSEAS Trans. Heat and Mass Trans., 14 (2019) 38-44.
  • Tadashi Watanabe, “Comparison of Two-Phase Critical Flow Models for Estimation of Leak Flow Rate through Cracks,” Int. J. Nucl. and Quantum Eng., 13 (2019) 516-519.

2018

  • Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI, “Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics and structural analyses,” Fron. Mech. Eng., (2018)

2017

  • Tadashi Watanabe, “Combustion Analysis of Suspended Sodium Droplet,” Int. J. Mechanical and Mechatronics Eng., 11 (2017) 1853-1856.

2016

  • Tadashi Watanabe, “Deformation of a rotating two-lobed droplet,” Int. J. Math. Models and Methods in Applied Sci., 10 (2016) 179-184.

2015

  • Hiroyuki Kitahata, Rui Tanaka, Yuki Koyano, Satoshi Matsumoto, Katuhiro Nishinari, Tadashi Watanabe, Koji Hasegawa, Tetsuya Kanagawa, Akiko Kaneko and Yutaka Abe, “Oscillation of a rotating levitated droplet: Analysis with a mechanical model,” Physical Review E, 92, 062904(2015)062904-1 \UTF{2013} 062904-8.
  • Qingyun Zeng, Jiejin Cai, Huaqiang Yin, Xingtuan Yang, Tadashi Watanabe, “Numerical Simulation of single bubble condensation in subcooled flow using OpenFOAM,” Prog. Nucl. Energy, 83 (2015) 336-346.
  • Tadashi Watanabe, “Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents,” World Academy of Science, Engineering and Technology, Int. J. of Mech., Aero., Ind., Mechatronic and Manufacturing Eng., 9 (2015) 1439-1443.

2014

  • Tadashi Watanabe, Yoshinari Anoda, Masahito Takano, “System-CFD coupled simulations of flow instability in steam generator U tubes,” Annals Nucl. Energy, 70 (2014) 141-146.

2013

  • Tadashi Watanabe, “Numerical Simulation of oscillating flow field including a droplet,” Int. J. Multiphysics, 7 (2013) 19-30.
  • Tadashi Watanabe, Yoshinari Anoda, Masahito Takano, “Stability of single-phase natural-circulation flows in steam generator U tubes,” Annals of Nucl. Energy, 60 (2013) 344-349.
  • Tadashi Watanabe, “Numerical simulation of the transient shape variation of a rotating liquid droplet,” World Academy Sci., Eng. Tech., 79(2013)1714-1718, 7 (2013) 1996-2000.

2012

  • T. Watanabe, M. Ishigaki, M. Hirano, “Analysis of BWR long-term station blackout accident using TRAC-BF1,” Annals of Nucl. Energy, 49, pp. 223-226, (2012)
  • Tadashi Watanabe, “On the numerical approach for simulating reactor thermal hydraulics under seismic conditions,” Annals of Nucl. Energy, 49 (2012) 200-206.
  • Masahiro Ishigaki, Tadashi Watanabe and Hideo Nakamura, “Numerical simulation of two-phase critical flow with the phase change in the nozzle tube,” J. Power and Energy Sys., 6 (2012) 264-274.

国際会議

2022

  • S. Soma, M. Ishigaki, S. Abe, Y. Sibamoto, “MEASUREMENT OF VELOCITY AND TEMPERATURE PROFILES IN BOUNDARY LAYER WITH STEAM CONDENSATION”, Proceedings of The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 35503, March (2022).

2020

  • Tadashi Watanabe, “Multiscale accident analysis for reliable safety evaluation of nuclear reactors,” MULTIPHYSICS 2020, 10-11, December 2020, virtual (2020).

2019

  • Tadashi Watanabe, Jinya Katsuyama, Akihiro Mano, “Comparison of Two-Phase Critical Flow Models for Estimation of Leak Flow Rate through Cracks,” INCRA 2019, Italy, December (2019).
  • Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li, “Effect of coolant water temperature of ECCS on failure probability of RPV”, PVP2019, USA, July (2019).

2018

  • T. Watanabe, M. Ishigaki, J. Katsuyama, “Analyses of LSTF Experiment and PWR Plant for 5% Cold-Leg Break Loss of Coolant Accident”, NUTHOS-12, China, October, (2018)
  • M. Ishigaki, T. Watanabe, “Numerical Simulation of Natural Circulation Experiment under Asymmetric Cooldown using LSTF”, NUTHOS-12, China, October, (2018)

2017

  • Tadashi Watanabe, “Combustion Analysis of Suspended Sodium Droplet,” ICFMTE 2017, France, November (2017).

2016

  • Shumpei Uno, Jinya Katsuyama, Tadashi Watanabe, Yinsheng Li, “Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses”, PVP2016, Canada, July (2016).
  • Tadashi Watanabe, “Numerical Simulation of Sodium Droplet Combustion,” ACSM 2016, Thailand, September (2016).

2015

  • Tadashi Watanabe, “Rotation and Deformation of a Levitated Droplet,” FMA ’15, Italy, June (2015).
  • Tadashi Watanabe, “Effects of ECCS on the Cold-Leg Fluid Temperature during SGTR Accidents,” ICESET2015, Germany, September (2015).

2014

  • Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa, Tadashi Watanabe, Yutaka Nishiyama,“Study on structural integrity assessment of reactor pressure vessel based on three-dimensional thermal-hydraulics and structural analyses”, PVP2014, USA, July (2014).

2013

  • T. Watanabe, “Numerical Simulation of the Oscillating Flow around a Droplet,” Fluids ’13, Italy, January (2013).
  • T. Watanabe, “Numerical Simulation of the Transient Shape Variation of a Rotating Liquid Droplet,” ICFMTE 2013, Switzerland, July (2013).
  • Qingyun Zeng, Jiejin Cai and Tadashi Watanabe, “Simulation of Oscillating Free Interface Behavior by Using OpenFOAM,” ICONE21, China, July (2013).

2012

  • Ishigaki, M., Watanabe, T., and Nakamura, H., “Numerical Simulation of Two-phase Critical Flow in a Convergent-Divergent Nozzle,” CFD4NRS-4, Korea, September (2012).

国内学会

2023

  • 上田，渡辺，石垣，“蒸気発生器伝熱管複数本破断(MSGTR)における破断位置の影響の検討”，日本原子力学会2023年秋の大会，名古屋（2023）
  • 石垣，廣瀬，永井，“大型格納容器実験装置における自然対流による成層浸食挙動のデータ同化を用いた解析”，第37回数値流体力学シンポジウム，名古屋 (2023)

2022

  • 石垣，廣瀬，永井，渡辺，“自然対流のアンサンブルカルマンフィルターによるデータ同化解析”, 第20回日本流体力学会中部支部講演会，福井（2022)
  • 石垣，廣瀬，安部，永井，渡辺，“大型格納容器実験装置CIGMA内熱流動解析へのデータ同化の適用; 観測データの配置および点数に関する検討”， 日本原子力学会2022年秋の大会，茨城 (2022)

2021

  • 石垣，廣瀬，安部，永井，渡辺，“自然対流挙動のカルマンフィルターによるデータ同化解析”, 日本流体力学会年会 2021，オンライン，(2021)

2020

  • 阿部豊、松本聡、西成活裕、渡辺正、金子暁子、北畑裕之、長谷川浩司、須田捷生、渡辺輝光、本田恒太、“浮遊液滴非線形ダイナミクス研究報告”、第35回宇宙環境利用シンポジウム、オンライン（2020）

2019

  • 渡辺正、石垣将宏、勝山仁哉、“LSTF実験及びPWRプラントの冷却材喪失事故解析“、日本原子力学会2019年春の年会、茨城(2019)

2018

  • 勝山仁哉、眞崎浩一、李銀生、渡辺正、“原子炉圧力容器の破損確立に及ぼす過渡条件の影響”、日本原子力学会2018年秋の大会、岡山(2018)

2017

  • 宇埜正美、青柳光裕、渡辺正、山本郁夫、河口宗道、土井大輔、伊藤啓、矢田浩喜、安藤勝訓、月森和之、“ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発：（17）成果の全体概要“、日本原子力学会2017年秋の大会、北海道(2017)
  • 渡辺正、“ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発：（19）ナトリウム液滴燃焼のVOF法による解析“、日本原子力学会2017年秋の大会、北海道(2017)

2016

  • 渡辺正、“非軸対称回転液滴の数値シミュレーション”、流体工学部門講演会、山口（2016）

2015

  • 阿部豊、松本聡、渡辺正、西成活裕、金子暁子、北畑裕之、長谷川浩司、金川哲也、“浮遊液滴非線形ダイナミクス研究報告”、第29回宇宙環境利用シンポジウム、神奈川（2015）
  • 青柳光裕、浜瀬枝里菜、大野修司、山田貴大、渡辺正、宇埜正美、“ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発：（2）ナトリウム燃焼時の熱影響評価手法の開発“、日本原子力学会2015年春の年会、茨城(2015)
  • 松岡浩、渡辺正、”直接数値シミュレーションの早期実用化を目指した整数型格子ボルツマン法による非熱流体過渡変化解析“、JHPCN学際大規模情報基盤共同利用共同研究拠点第７回シンポジウム、東京（2015）

2014

  • 渡辺正、安濃田良成、高野雅仁、石垣将宏、“蒸気発生器U字管内単相自然循環の安定性解析”、日本原子力学会2014年春の年会、東京(2014)
  • 松岡浩、渡辺正、”直接数値シミュレーションの早期実用化を目指した整数型格子ボルツマン法による非熱流体過渡変化解析“、JHPCN学際大規模情報基盤共同利用共同研究拠点第6回シンポジウム、東京（2014）
  • 渡辺正、“回転液滴の変形挙動”、日本機械学会2014年度年次大会、東京（2014）
  • 勝又玄七郎、勝山仁哉、鬼沢邦雄、西山裕孝、李銀生、渡辺正、“三次元熱流動解析による加圧熱衝撃時の温度条件の検討”、日本原子力学会2014年秋の大会、京都(2014)

2013

  • 渡辺正、安濃田良成、高野雅仁、“PWR全交流電源喪失時の蒸気発生器自然循環挙動”、日本原子力学会2013年春の年会、大阪(2013)
  • 渡辺正、安濃田良成、高野雅仁、“PWR全交流電源喪失時の蒸気発生器自然循環の解析”、日本原子力学会2013年秋の大会、青森(2013)

2012

  • 石垣将宏，渡辺正，竹田武司、中村秀夫，“OECD/NEA ROSA-2プロジェクト(2)片側SG冷却材喪失時の自然循環による冷却実験”，日本原子力学会2012年秋の大会、広島(2012)
  • 安濃田良成、渡辺正、高野雅仁、“PWR全交流電源喪失時の蒸気発生器内多次元流動に関する解析”、日本原子力学会2012年秋の大会、広島(2012)