Kyushu University Academic Staff Educational and Research Activities Database
List of Presentations
Tatsuya Matsumoto Last modified date:2023.11.22

Assistant Professor / Nuclear Energy Systems / Department of Applied Quantum Physics and Nuclear Engineering / Faculty of Engineering


Presentations
1. M. Koga, K. Takanishi, T. Matsumoto, W. Liu, K. Morita, K. Nakamura, T. Kanai, Experimental Study on Aerosol Migration Behavior in Rectangular Penetrations, 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12), 2022.11.
2. Kazuya Gotou, Wei Liu, Tsutaya Matumoto, Koji Morita, FLOW CHARACTERISTICS IN RECTANGULAR MICRO-CHANNELS WITH HIGH ASPECT RATIOS, 19th INTERNATIONAL TOPICAL MEETING ON NUCLEAR REACTOR THERMAL HYDRAULICS (NURETH 19), 2022.03.
3. Md. Abdur Rafiq Akand, Kei Kitahara, Tatsuya Matsumoto, Wei Liu, Koji Morita, A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling., 28th International Conference on Nuclear Engineering (ICONE 28), 2021.08.
4. M. A. Rafiq Akand, Kei Kitahara, Tatsuya Matsumoto, Wei Liu, Koji Morita, An Improved Mechanistic Model for Prediction of Bubble Lift-off Diameter in Subcooled Flow Boiling for Inclined Heating Surface, 日本原子力学会「2021年春の年会」, 2021.03.
5. M. A. Rafiq Akand, T. Matsumoto, W. Liu and K. Morita, A Modified Liquid Sublayer Dryout Model For Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition, International Topical Meeting on Advances in Thermal Hydraulics 2020, 2020.10.
6. Md Abdur Rafiq Akand, Kei Kitahara, Tatsuya Matsumoto, Wei Liu, Koji Morita, Bubble Lift-off Size in Subcooled Flow Boiling for Inclined Heating Surface, 日本原子力学会「2020年秋の大会」, 2020.09.
7. M. A. Rafiq Akand, Tatsuya Matsumoto, Wei Liu, Koji Morita, Prediction of Net Vapor Generation Point for Heating Surface with Different Inclination Angle at IVR Condition, 日本原子力学会「2020年春の年会」, 2020.03.
8. S. HOSOMI, T. AKASHI, T. MATSUMOTO, W. LIU, K. MORITA, K. TAKAMATSU, Experimental Study on Heat Removal Performance of A New Reactor Cavity Cooling System (RCCS), 11th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11), 2018.11.
9. M. KATO, K. FUNAKOSHI, X. LIU, T. MATSUMOTO, W. LIU, K. MORITA, K. KAMIYAMA, Validation of Three-Dimensional Finite-Volume-Particle Method for Simulation of Liquid-Liquid Mixing Flow Behavior, 11th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11), 2018.11.
10. R. KAWATA, Y. OHARA, M.A.R. SHEIKH, X. LIU, T. MATSUMOTO, K. MORITA, L. GUO, K. KAMIYAMA, T. SUZUKI, Numerical Simulation of Solid-Particle Sedimentation Behavior Using a Multi-Fluid Model Coupled with DEM, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 2017.09.
11. L.H.S. PHAN, P.M. NGO, F. MATSUOKA, R. MIURA, T. MATSUMOTO, K. MORITA, Experimental Study on Self-Leveling Behavior of Binary-Mixed Particles in Cylindrical Bed Using Gas-Injection Method, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 2017.09.
12. M.A.R. Sheikh, E. Son, M.KAMIYAMA, T. Morioka, T. MATSUMOTO, K. MORITA, K. Matsuba, K. KAmiyama, T.SUZUKI, Experimental Database for Bed Formation Behaviors of Solid Particles, 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), 2016.11.
13. M.A.R. Sheikh, E. Son, M.KAMIYAMA, T. Morioka, T. MATSUMOTO, K. MORITA, K. Matsuba, K. KAmiyama, T.SUZUKI, Experimental Investigation on Characteristics of Mixed Particle Debris in Sedimentation and Bed Formation Behavior, 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), 2016.10.
14. T. Takamatsu, T. Matsumoto, K. Morita, New Reactor Cavity Cooling System with A Novel Shape and Passive Safety Features, International Congress on Advances in Nuclear Power Plants, ICAPP 2016, 2016.04.
15. FUKUDA S., ZHANG H., TAKATA N., MATSUMOTO T., KOYAMA S., Condensation of R1234ze(Z) inside a vertical plate-fin Heat Exchanger, The 24th IIR International Congress of Refrigeration, 2015.08.
16. K. MORITA, T. MATSUMOTO, S. TAKETA, S. NISHI, S.CHENG, T.SUZUKI, Y.TOBITA, Validation of New Empirical Model for Self-Leveling Behavior of Cylindrical Particle Beds Based on Experimental Database, The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10) , 2014.12.
17. K. MORITA, T. MATSUMOTO, M. EMURA, T. ABE, I.TATEWAKI, H.ENDO, INVESTIGATION ON SLOSHING RESPONSE OF LIQUID IN A 2D POOL AGAINST HYDRAULIC DISTURBANCE, The Ninth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), 2014.11.
18. M.SHAMSUZZAMAN, T. MATSUMOTO, M.KAMIYAMA, T.MORIOKA, K. MORITA, H.TAGAMI, T.SUZUKI, Y.TOBITA, EXPERIMENTAL STUDY ON SEDIMENTATION BEHAVIOR OF CORE DEBRIS , The Ninth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), 2014.11.
19. M.SHAMSUZZAMAN, T.HORIE, F.FUKE, T.KAI, B.ZHANG, Tatsuya Matsumoto, Koji Morita, H.TAGAMI, T.SUZUKI, Y.TOBITA, Experimental Evaluation of Debris Bed Characteristics in Particulate Debris Sedimentation Behaviour, 2013 21th International Conference on Nuclear Engineering (ICONE21), 2013.07.
20. S.CHENG, H.YAMANO, T.SUZUKI, Y.TOBITA, Y. Nakamura, S. Taketa, S. Nishi, B.ZHANG, Tatsuya Matsumoto, Koji Morita, Recent Knowledge from an Experimental Investigation on Self-Leveling Behavior of Debris Bed, 2013 21th International Conference on Nuclear Engineering (ICONE21), 2013.07.
21. M.SHAMSUZZAMAN, T.HORIE, F.FUKE, T.KAI, B.ZHANG, Tatsuya Matsumoto, Koji Morita, H.TAGAMI, T.SUZUKI, Y.TOBITA, Experimental Investigation of Debris Sedimentation Behavior on Bed Formation Characteristics, 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), 2012.12.
22. S.CHENG, H.YAMANO, T.SUZUKI, Y.TOBITA, Y.GONDAI, Y.NAKAMURA, B.ZHANG, Tatsuya Matsumoto, Koji Morita, An Experimental Study on Self-Leveling Behavior of Debris Beds with Comparatively Higher Gas Velocities, 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), 2012.12.
23. H.YAMANO, T.SUZUKI, Y.TOBITA, Tatsuya Matsumoto, Koji Morita, Validation of the SIMMER-IV Severe Accident Computer Code on Three-Dimensional Sloshing, 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), 2012.12.
24. B.ZHANG, Tatsuya Matsumoto, Koji Morita, H.YAMANO, H.TAGAMI, T.SUZUKI, Y.TOBITA, Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III, 2012 20th International Conference on Nuclear Engineering collocated with ASME 2012 Power Conference (ICONE20-POWER2012), 2012.08.