研究業績

2016 Academic Year

【Journal Paper】

  1. S. Miwa, C. Kane, and S. Revankar
    “Microscopic Fluid Dynamic Simulation of the Metal Foam using Idealized Cell Structure”
    Transport in Porous Media (2016)  Vol. 115 (1), 35-51
  2. S. Miwa, H. Endo, T. Moribe, H. Sakashita, M. Mori, and T. Hibiki
    “Investigation of the Thermal-hydraulics Characteristics of the Supersonic Steam Injector”
    Applied Thermal Engineering (2016) Vol. 109, Part A, 261-271
  3. T. Ogura, T. Matsumoto, S. Miwa, H. Sakashita, M. Mori, and T. Hibiki
    “Experimental Study on Molten Metal Spreading and Deposition Behaviors” (Submitted)
  4. T. Matsumoto, S. Miwa, H. Sakashita, and M. Mori
    “Scaling Analysis of the Spreading and Deposition Behaviors of Molten-Core-Simulated Metals” (Submitted)

【International and Domestic Conferences】

  1. T. Matsumoto, T. Ogura, S. Miwa, and M. Mori 【ポスター賞】
    “Experimental Investigation of Spreading and Deposition Behaviors of Moten Core Debris”
    The 20th Pacific Basin Nuclear Conference (PBNC 2016), April 5-9, 2016, Beijing, China
  2. H. Endo, S. Miwa, and M. Mori
    “Characteristics of the Steam Injector for the Static Reactor Cooling Systems”
    International Conference on Advances in Nuclear Power Plant (ICAPP), April 17-20, 2016, Hyatt Regency San Francisco, San Francisco, CA
  3. S. Miwa, Y. Liu, T. Hibiki and M. Mori
    “Investigation of Gas-Liquid Two-phase Flow Induced Vibration Characteristics”
    International Conference on Multiphase Flow (ICMF), May 22-27, 2016, Palazzo dei Congressi, Firenze, Italy
  4. M. Mori, T. Matsumoto, T. Ogura, and S. Miwa
    “Spreading Behaviors on Molten-Metal Falling-Flow at Elevated Temperatures in Nuclear Severe Accident Conditions”
    International Conference on Multiphase Flow (ICMF), May 22-27, 2016, Palazzo dei Congressi, Firenze, Italy
  5. H. Mitsuda, K. Yamada, S. Miwa, H. Sakashita, and M. Mori
    “福島第一原子力発電所燃料デブリ取出し工法に係る炉内熱流動評価解析”
    第21回動力・エネルギー技術シンポジウム、横浜市開港記念会館、2016年6月16~17日
  6. S. Miwa
    “The Use of Dynamic Force Signals for Two-phase Flow Regime Identification”
    The 24th International Conference on Nuclear Engineering (ICONE-24), June 26-30, 2016, Charlotte Convention Center, Charlotte, NC, USA
  7. S. Miwa 【招待講演】
    “Experimental Studies on Multiphase Flow for Improved Engineering Systems”
    Invited Seminar, August 12, 2016 Okinawa Institute of Science and Technology Graduate University, Okinawa, Japan
  8. T. Matsumoto, T. Ogura, S. Nishigaki, S. Miwa, H. Sakashita, and M. Mori
    “Experimental Investigation of Spreading and Deposition Behaviors of Molten Core Debris”
    The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NUTHOS-11), Operation and Safety, October 9-13, 2016, Gyeongju, Korea.
  9. H. Mitsuda, K. Yamada, S. Miwa, H. Sakashita, M. Mori
    “Evaluation of the In-Vessel Heat Transfer Characteristics for the Fukushima Daiichi Nuclear Power Plant Debris Removal”
    The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NUTHOS-11), Operation and Safety, October 9-13, 2016, Gyeongju, Korea.
  10. J. Yang, D.Y. Lee, S. Miwa, and S.W. Chen
    “Overview of filtered containment venting in Asia NPPs”
    The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NUTHOS-11), Operation and Safety, October 9-13, 2016, Gyeongju, Korea.

 

2015 Academic Year

【Journal Paper】

  1. S. Miwa, T. Hibiki, and M. Mori
    “Analysis of Flow Induced Vibration due to Stratified Wavy Two-phase Flow”,
    Journal of Fluids Engineering (2016) , Vol. 138 (9), doi: 10.1115/1.4033371
  2. H. Sakashita
    “Temeprature Measurements Near the Heating Surface at High Heat Fluxes in Pool Boiling of 2-Propanol/ Water Mixtures”
    International Journal of Heat and Mass Transfer (2016), Vol. 93, 1000-1007.
  3. Hamada, H. Kokami, S. Miwa, H. Sakashita, and M. Mori
    “Assessment of the Countermeasure Improvement of ABWR using RETRAN-3D”
    Annals of Nuclear Energy (2016), Vol. 94, 223-229.

【International and Domestic Conferences】

  1. Kokami, Y. Hamada, S. Miwa, H. Sakashita, and M. Mori
    “Evaluation of Accident Mitigation Procedure with Isolation Condensers for LWR by Reactor Simulation Analyses” International Congress on Advances in Nuclear Power Plants (ICAPP-2015) May 3-6, 2015, Nice, France
  2. S. Miwa, T. Hibiki, and M. Mori
    “Development of Internal Two-phase Flow Induced Force Fluctuations Model”
    Japan-US Seminar on Two-phase Flow Dynamics, May 10-15, 2015, Purdue University, IN, USA
  3. S. Miwa, T. Hibiki, and M. Mori 【日本機械学会優秀講演賞】
    “Prediction of Two-phase Flow Induced Vibration using Artificial Void Signal”
    Proceedings of the 2015 23rd International Conference on Nuclear Engineering (ICONE-23) May 17-21, 2015, Makuhari, Japan CD-ROM, ICONE23-2165
  4. T. Ogura, M. Mori, C. W. Forsberg, S. Miwa, and H. Sakashita
    “Design Considerations for Insulation System for Fluoride Salt Cooled High Temperature Reactor under Beyond Design Basis Accident Conditions”
    Proceedings of the 2015 23rd International Conference on Nuclear Engineering (ICONE-23) May 17-21, 2015, Makuhari, Japan CD-ROM, ICONE23-2171
  5. Y. Okuyama, S. Miwa, H. Sakashita, and M. Mori
    “Atmospheric Diffusion Numerical Simulation Analysis of Cesium that takes into account the Wet Deposition”
    Proceedings of the 2015 23rd International Conference on Nuclear Engineering (ICONE-23) May 17-21, 2015, Makuhari, Japan CD-ROM, ICONE23-1854
  6. H. Kokami, S. Miwa, H. Sakashita, and M. Mori
    “Severe Accident Analysis of LWR equipped with Isolation Condensers employing RETRAN/ MOD4”
    Proceedings of the 2015 23rd International Conference on Nuclear Engineering (ICONE-23) May 17-21, 2015, Makuhari, Japan CD-ROM, ICONE23-2177
  7. K. Shimamura, S. Miwa, H. Sakashita, and M. Mori
    “Molten Core Concrete Interaction at Containment Sump Pit under Severe Accident Condition”
    Proceedings of the 2015 23rd International Conference on Nuclear Engineering (ICONE-23) May 17-21, 2015, Makuhari, Japan CD-ROM, ICONE23-2188
  8. S. Miwa, Y. Takeya, H. Endo, and M. Mori
    “Experimental Investigation of the High Performance Steam Injector Operation”
    16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 30-Sept 4, 2015, Hyatt Regency, Chicago IL
  9. S. Miwa 【招待講演】
    “Thermal-Hydraulics and Reactor Safety Research after Fukushima Accident”
    2015 International Symposium on Low Carbon Energy Technology and Industry Policy, Dec 4th, 2015, National Tsing Hua University, Taiwan
  10. S. Miwa 【招待講演】
    “Thermal-Hydraulics and Multiphase Flow Research after Fukushima Accident”
    Invited Seminar, Jan 4th, 2016, Kyungpook National University, Daegu, Korea
  11. Matsumoto, A. Kobayashi, S. Miwa, H. Sakashita, M. Mori
    “高温溶融金属の凝固を伴う拡散流動に関する研究”
    第20回日本機械学会動力エネルギー技術シンポジウム　平成27年6月18~19日
  12. S. Miwa, Y. Takeya, H. Endo, M. Mori
    混相流シンポジウム2015 高知高知工科大学
  13. H. Mitsuda, S. Miwa, H. Sakashita, M. Mori 【日本混相流学会ベストプレゼンテーション賞】
    混相流シンポジウム2015 高知工科大学
  14. Y. Tajiri, S. Miwa, and M. Mori
    熱工学コンファレンス2015 大阪大学
  15. H. Endo, S. Miwa, and M. Mori
    “静的安全炉心注水系としての蒸気インジェクタ作動特性に関する研究”
    日本原子力学会北海道支部第33回研究発表会，北海道大学工学部，2016年2月16日
  16. T. Matsumoto, T. Ogura, S. Miwa, H. Sakashita, and M. Mori
    “高温溶融金属の床面衝突を伴う拡がりと堆積挙動に関する実験研究”
    日本原子力学会北海道支部第33回研究発表会，北海道大学工学部，2016年2月16日
  17. Y. Shoji, S. Miwa, H. Sakashita, and M. Mori
    “高圧域におけるプール沸騰限界熱流束に対する濡れ性の影響に関する研究”
    日本機械学会第43回学生員卒業研究発表講演会，函館高専，2016年3月7日
  18. T. Moribe, S. Miwa, H. Sakashita, and M. Mori 【日本機械学会北海道支部ベストプレゼンテーション賞】
    “蒸気インジェクタの作動範囲と吐出性能に関する研究”
    日本機械学会第43回学生員卒業研究発表講演会，函館高専，2016年3月7日
  19. Ogura, T. Matsumoto, Z.Y. Ma, S. Nishigaki, S. Miwa, H. Sakashita, and M. Mori　【日本原子力学会優秀講演賞】
    “溶融炉心デブリ拡がり挙動解明に関する実験的研究”
    原子力学会春の年会東北大学川内キャンパス，2016年3月26~28日

【Master Thesis】

  1. 奥山祐太
    “Numerical Simulation Analysis on Atmospheric Diffusion of Radioactive Materials affected by  Rain and Snow falling”
  2. 小倉貴仁
    “Experimental Study on Spreading and Deposition Behaviors with Impingement of Molten-Core-Simulated Metals”
  3. 鴻上弘毅
    “System Design on Accident Mitigation of Pressurized Water Reactor Equipped with Isolation Condenser at SBO”
  4. 嶋村和也
    “Analytical Evaluation on Erosion Development of PCV Concrete by Molten Core Concrete Interaction ”
  5. 田尻裕太郎
    “Classification of two-phase flow regimes based on force fluctuation signals using artificial neural network”

【Graduation Thesis】

  1. 山田　快
    “Evaluation of Heat Transfer Characteristics in Containment Vessel for the Debris Removal of the Fukushima Daiichi Nuclear Power Plant”
  2. 西垣　宙
    “Analysis of solidification and spreading behaviors of high temperature molten metal by CFD code”
  3. 井澤　和秀
    “Effects of radiation heat transfer on core fuel rods behaviors during SBO at the Fukushima Daiichi Nuclear Power Plant Unit 1”
  4. 森部　貴裕
    “Study on Operable Ranges and Discharge Performance of Steam Injector System”
  5. 荘司　優介
    “Effects of surface wettability on critical heat flux at high pressures in pool boiling”

2014 Academic Year

【Journal Paper】

  1. S. Miwa, Y. Liu, T. Hibiki , M. Ishii, H. Morita, Y. Kondo, K. Tanimoto  【日本機械学会論文賞】
    “Study of Unsteady Gas-Liquid Two-phase Flow Induced Force Fluctuation (Part 1: Evaluation and Modeling of Two-phase Flow Induced Force Fluctuation)”
    Transactions of the JSME (in Japanese) (2014), Vol. 80, No. 809, 1-11
  2. S. Miwa, Y. Liu, T. Hibiki , M. Ishii, H. Morita, Y. Kondo, K. Tanimoto
    “Study of Unsteady Gas-Liquid Two-phase Flow Induced Force Fluctuation (Part 2: Horizontal-downward Two-phase Flow)”
    Transactions of the JSME (in Japanese) (2014), Vol. 80, No. 811, 1-11
  3. Y. Takeya, S. Miwa, M. Mori, and T. Hibiki
    “Application of Steam Injector to Improved Safety of Light Water Reactors”
    Progress in Nuclear Energy (2015), Vol. 75, 80-100, DOI: 10.1016/j.pnucene.2014.07.045
  4. S. Miwa, T. Hibiki, and M. Mori
    “Two-phase Flow Induced Vibration in Piping Systems”
    Progress in Nuclear Energy (2015), Vol.78, 270-287, DOI: 10.1016/j.pnucene.2014.10.003
  5. S. Chen, S. Miwa, M. Griffiths, S. Shi, T. Hibiki, and M. Ishii
    “Experimental Study of Gas-Liquid Two-phase Flow through Packed Bed under Natural Circulation Conditions”
    Journal of Nuclear Science and Technology (2015), Vol. 53, 34-47

【Book Chapter/ Review】

  1. S. Miwa, T. Hibiki, and M. Mori
    “FIV and Internal Two-phase Flow”
    Piping Technology, Japan Industrial Publishing Co., Ltd., January 2015 Issue

【International and Domestic Conferences】

  1. T. Hosaka, Y. Tsuji, S. Miwa, H. Sakashita, and M. Mori
    “原子力発電所における安全対策の新基準への対応に関する一考察”
    日本原子力学会「２０１４年春の大会」東京都市大学，世田谷キャンパス 2014年3月26日～28日
  2. S. Miwa and M. Mori
    “Development of Two-phase Flow Induced Force Fluctuations Predictive Tools”
    Proceedings of the 19th National Symposium on Power and Energy Systems (SPES2014) June 26-27, 2014, Fukui, Japan, pp. 179-180
  3. Y. Takeya, S. Miwa, M. Mori, and H. Sakashita
    “Steam Injector Core Injection Characteristics by Water-Steam Direct Condensation Applied for LWR Severe Accident”
    Proceedings of the 19th National Symposium on Power and Energy Systems (SPES2014) June 26-27, 2014, Fukui, Japan, pp. 251-252
  4. A. Kobayashi, S. Miwa, and M. Mori 【ICONE22国際会議ベストポスター賞】
    “Analytical Evaluation of Debris Cooling and Spreading Behaviors at Molten Core in Severe Accident”
    Proceedings of the 2014 22nd International Conference on Nuclear Engineering (ICONE22) July 7-11, 2014, Prague, Czech Republic, CD-ROM, ICONE22-30035
  5. S. Miwa, Y. Liu, T. Hibiki, M. Ishii, Y. Kondo, H. Morita, and K. Tanimoto
    “Two-phase Flow Induced Force Fluctuations on Pipe Bend”
    Proceedings of the 2014 22nd International Conference on Nuclear Engineering (ICONE22) July 7-11, 2014, Prague, Czech Republic, CD-ROM, ICONE22-30573
  6. T. Ogura, M. Mori, H. Sakashita, S. Miwa, J. Nakata
    “Performance Evaluation of SCS for AHTR and Time Assessment of Operation Procedures”
    Proceedings of the 2014 22nd International Conference on Nuclear Engineering (ICONE22) July 7-11, 2014, Prague, Czech Republic, CD-ROM, ICONE22-30790
  7. T. Murata, S. Miwa, H. Sakashita, and M. Mori
    “Effects of Snowing and Raining on Atmospheric Diffusion of Cesium in Severe Accident”
    The Japanese Society for Multiphase Flow, Multiphase Flow Symposium 2014, July 28 – 30, 2014, Sapporo, Japan
  8. S. Miwa, A. Kobayashi, M. Mori
    “Evaluation of Debris Spreading Behavior During Severe Accident”
    International Workshop on Nuclear Safety and Severe Accident 2014 (NUSSA-2014), Kashiwa, Chiba, Japan, September 3-5, 2014
  9. S. Miwa
    “Unsteady Gas-Liquid Two-phase Flow Induced Force Fluctuations”
    Young Researcher’s Forum, Thermal-Hydraulics Division, Atomic Energy Society of Japan, Kyoto, Japan, September 10-11, 2014
  10. Y. Hamada, H. Kokami, S. Miwa, H. Sakashita, and M. Mori
    “Coutermeasures to Improve LWR Safety Level in Design and Operation Perspectives by Reactor Simulation Analysis”
    Proceedings of the 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-9), Buyeo, Korea, November 16-19, 2014
  11. T. Murata, S. Miwa, H. Sakashita, and M. Mori
    “高温ガス炉発電および熱利用による融雪・地域暖房システムの最適設計研究”
    日本原子力学会北海道支部第３２回研究発表会，北海道大学大学院工学研究院　平成２６年１２月１６日
  12. Y. Hamada, H. Kokami, S. Miwa, H. Sakashita, and M. Mori 【原子力学会北海道支部奨励賞】
    “原子力発電所事故解析による設計運転最適化と安全性向上に関する研究”
    日本原子力学会北海道支部第３２回研究発表会，北海道大学大学院工学研究院　平成２６年１２月１６日
  13. Y. Tsuji, S. Miwa, and M. Mori
    “Evaluation of Safety Issues on Newly Regulated Nuclear Power Plant by Tsunami-Level 1 PRA”
    Proceedings of the 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, December 14-18.2014

【Master Thesis】

  1. 小林 明弘
    “Experiment on Impingement and Spreading Behaviors of Molten Metal”
  2. 竹谷 勇人
    “Study of Steam Injector for Static Core Cooling System at Station Blackout in Light Water Reactor”
  3. 濱田 悠平
    “Countermeasures to Improve LWR Safety Level in Design and Operation Perspectives by Reactor Simulation Analysis”
  4. 村田 哲也
    “Utilization of GHTR300 Waste Heat for District Heating and Snow Melting”

【Graduation Thesis】

  1. 遠藤 宏純
    “A Study of the Characteristics of the Steam Injector for Static Reactor Cooling Systems”
  2. 松下 貴博
    “Critical Heat Flux in Pool Boiling under High Pressure Condition”
  3. 松本 竜輝
    “Computational Analysis of Falling Molten Metal”
  4. 満田 光
    “Drain Discharge Technology for Wall Thinning in Piping Systems by Computational Analysis”

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