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Tatsuya Matsumoto Last modified date:2021.06.11



Graduate School
Undergraduate School


Homepage
https://kyushu-u.pure.elsevier.com/en/persons/tatsuya-matsumoto
 Reseacher Profiling Tool Kyushu University Pure
http://www.qpn.kyushu-u.ac.jp/lab6/
Department of Applied Quantum Physics and Nuclear Engineering・Nuclear Energy Systems .
Academic Degree
Doctor of Engineering
Country of degree conferring institution (Overseas)
No
Field of Specialization
Heat Transfer, Thermal Hydaulics
Total Priod of education and research career in the foreign country
00years02months
Research
Research Interests
  • Investigation for thermal hydraulic flow behavior in core
    keyword : debris bed, solid-gas-liquid,three-phase flow
    2018.04.
  • Investigation for thermal hydraulic flow behavior in a deberis bed
    keyword : debris bed, solid-gas-liquid,three-phase flow
    2017.04.
  • Development of palte-fin heat exchenger
    keyword : development, plate-fin, heat exchenger, condensation
    2014.10.
  • Experimental research for reactor coolability of HTTR
    keyword : reactor vessele, coolability, HTTR
    2014.09.
  • Experimental research for sedimentation behavior of debris on core disruptive accident
    keyword : core disruptive accident, debris, sedimentation
    2011.09.
  • Experimental research for sloshing behavior in Reactor Core Pool
    keyword : Core Pool, Sloshing
    2011.10.
  • Investigation for three phase flow behavior in a deberis bed
    keyword : debris bed, solid-gas-liquid,three-phase flow
    2009.04.
  • Research on Molten Metal Freezing behavior in a Fuel Pin Bundle
    keyword : Severe accident, Core Disruptive Accident, Fuel Pin Bundle, Melting, Freezing
    2007.04~2012.03.
  • Research on Self-Leveling Behavior in a Debris Bed during Core Disruptive Accidents
    keyword : Severe Accident, Core Disruptive Accident, Molten Core, Debris Bed, Self-Leveling Behavior
    2005.04.
  • Research on Pressure Transient Behavior of Solid Particle
    keyword : Solid Particle, Solid-Gas-Liquid Three Phase Flow, Pressure Transient Behavior
    2004.01~2006.07.
  • Investigation of Phase Change Model in a Safety Analysis Code for Severe Accident of Fast Reactor
    keyword : Fast Reactor, Safety Analysis, Phase Change
    2000.04~2005.03.
  • Investigation of Numerical Analysis Method for Multi-Dimension, Gas-Liquid Two Phase Flow using Drift Flux Model
    keyword : Gas-Liquid Two Phase Flow, Drift Flux Model, Numerical Analysis
    2000.04~2002.03.
  • Research on Core Retention in Reactor Vessel in a Severe Accident of Light Water Reactor
    keyword : Severe Accident, Narrow Passage, Thermal Hydraulic Behavior, Critical Heat Flux
    2000.04~2003.03.
  • Research on Gas-Liquid Two Phase Flow in Passage with Noncircular Cross Section
    keyword : Free Surface, Condensation Heat Transfer
    2000.04~2005.01.
Academic Activities
Papers
1. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita, Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation, Annals of Nuclear Energy, 10.1016/j.anucene.2020.107867, 151, 1-11, 107867, 2021.02.
2. Md Abdur Rob Sheikh, Xiaoxing Liu, Tatsuya Matsumoto, Koji Morita, Liancheng Guo, Tohru SuzukiKenji Kamiyama, Numerical Simulation of the Solid Particle Sedimentation and Bed Formation Behaviors Using a Hybrid Method, Energies, 10.3390/en13195018, 13, 19, 1-15, 5018, 2020.09.
3. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita, Comparative methodology between actual RCCS and downscaled heat-removal test facility, Annals of Nuclear Energy, 10.1016/j.anucene.2019.07.025, 133, 830-836, 2019.11, Previously, a reactor cavity cooling system (RCCS) has been reported with passive safety features comprising of two continuous closed regions, namely an ex-reactor pressure vessel region and cooling region with a heat-transfer surface to ambient air. The novel shape of the RCCS allows it to efficiently remove heat released from the reactor pressure vessel (RPV) via thermal radiation and natural convection. The RCCS design significantly reduces the possibility of losing the heat sink for decay heat-removal during nuclear accidents including a station blackout by employing air as a working fluid and ambient air as ultimate heat sink. RCCS has the potential to stably and passively remove heat released from the RPV and decay heat following a reactor shutdown. The RCCS achieved a heat-removal rate of approximately 3 kW/m2. On the contrary, the heat fluxes from the RPV surface of the high temperature engineering test reactor and commercial high temperature gas-cooled reactors are 1.23–2.46 kW/m2 and approximately 3.0 kW/m2, respectively. In the previous report, the authors changed the adiabatic boundary conditions and considered the heat dissipation effect from the RPV region to ground through the RCCS wall via heat conduction; therefore, the authors could improve the system's heat-removal capability to increase its thermal reactor power level. Moreover, considering the possibilities for doubling the heat-transfer areas and increasing the emissivities, heat flux removed by the RCCS could potentially reach 7.0 kW/m2. Herein, the authors conduct a comparative methodology between an actual RCCS and a downscaled heat-removal test facility..
4. L.H.S. PHAN, P.M. NGO, R. MIURA, Y. TASAKI, T. MATSUMOTO, W. LIU, K. MORITA, Self-Leveling Behavior of Mixed Solid Particles in Cylindrical Bed Using Gas-Injection Method, Journal of Nuclear Science and Technology, 56, 1, 111-122, 2019.01.
5. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita, Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection, Annals of Nuclear Energy, 10.1016/j.anucene.2018.08.047, 122, 201-206, 2018.12, A previously-reported concept of reactor cavity cooling system (RCCS) with passive safety features consists of two continuous closed regions: an ex-reactor pressure vessel region and a cooling region with a heat-transfer surface to ambient air. The RCCS uses a novel shape to efficiently remove the heat released from the reactor pressure vessel (RPV) through thermal radiation and natural convection. Employing air as a working fluid and ambient air as an ultimate heat sink, the novel RCCS design strongly reduces the possibility of losing the heat sink for decay-heat-removal during nuclear accidents including a station blackout. The RCCS could stably and passively remove the heat released from the RPV and the decay heat after reactor shutdown. The previously-reported heat-removal rate of the RCCS was approximately 3 (kW/m2). The heat flux from the RPV surface of the High Temperature engineering Test Reactor (HTTR) is almost in the same range; 1.23–2.46 (kW/m2). In this paper, the authors address an improvement of heat-removal capability by considering potential of heat leakage due to heat conduction through the RCCS wall aimed at increasing a thermal reactor power level. Under the assumption of doubling the RCCS wall heat transfer area, a heat-flux removed by the RCCS could be doubled, such as approximately 6.2 (kW/m2)..
6. 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), Proc. of 11th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11), N11P0045, 2018.11.
7. MD A.R. SHEIKH, E. SON, M. KAMIYAMA, T. MORIOKA, T. MATSUMOTO, K. MORITA, K. MATSUBA, K. KAMIYAMA, T. SUZUKI, Sedimentation Behavior of Mixed Solid Particles, Journal of Nuclear Science and Technology, 55, 6, 623-633, 2018.06.
8. MD SHAMSUZZAMAN, T. HORIE, F. FUKE, M. KAMIYAMA, T. MORIOKA, T. MATSUMOTO, K. MORITA, H. TAGAMI, T. SUZUKI, Y. TOBITA, Experimental Study on Debris Bed Characteristics for the Sedimentation Behavior of Solid Particles Used as Simulant Debris, Annals of Nuclear Energy, 111, 474-486, 2018.01.
9. 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, Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Paper No. 20828, 2017.09.
10. 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, Proc. of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), N10P1135, 2016.11.
11. T. Takamatsu, T. Matsumoto, K. Morita, New Reactor Cavity Cooling System (RCCS) with Passive Safety Features: A Comparative Methodology between A Real RCCS and A Scaled-Down Heat-Removal Test Facility, Annals of Nuclear Energy, 96, 137-147, 2016.10.
12. 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, Proc. of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), N11P0029, 2016.10.
13. Koji Morita, Tatsuya Matsumoto, S.Nishi, T.Nishikido, S.Cheng, H.Tagami, T.Suzuki, Y.Tobita, A New Empirical Model for Self-Leveling Behavior of Cylindrical Particle Beds, Journal of Nuclear Science and Technology, 53, 5, 713-725, 2016.05.
14. T. Takamatsu, Tatsuya Matsumoto, Koji Morita, New Reactor Cavity Cooling System with A Novel Shape and Passive Safety Features, Proc. of International Congress on Advances in Nuclear Power Plants, ICAPP 2016, 2, 1250-1257, 2016.04.
15. FUKUDA S., ZHANG H., TAKATA N., MATSUMOTO T., KOYAMA S., Condensation of R1234ze(Z) inside a vertical plate-fin Heat Exchanger, Proceedings of the 24th IIR International Congress of Refrigeration, 361, 2015.08.
16. Koji Morita, Tatsuya 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), NUTHOS10-1299, 2014.12.
17. K. Morita, T. Matsumoto, Y.EMURA, T.ABE, I.TATEWAKI, H.ENDO, INVESTIGATION ON SLOSHING RESPONSE OF LIQUID IN A 2D POOL AGAINST HYDRAULIC DISTURBANCE, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety(NTHAS9), N9P0033, 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 Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety(NTHAS9), N9P0057, 2014.11.
19. S.CHENG, H.Tagami, H.YAMANO, T.SUZUKI, Y.TOBITA, S.Taketa, S.Nishi, B.ZHANG, Tatsuya Matsumoto, Koji Morita, Experimental Study and Empirical Model Development for Self-Leveling Behavior of Debris Bed Using Gas-Injection, Mechanical Engineering Journal, 51, 9, TEP0022, 2014.08.
20. S.CHENG, H.Tagami, H.YAMANO, T.SUZUKI, Y.TOBITA, S.Taketa, S.Nishi, T.Nishikido, B.ZHANG, Tatsuya Matsumoto, Koji Morita, An Investigation on Debris Bed Self-Leveling Behavior with Non-Spherical Particles, Journal of Nuclear Science and Technology, 51, 9, 1096-1106, 2014.03.
21. M.SHAMSUZZAMAN, B.ZHANG, T.HORIE, F.FUKE, T.KAI, T. Matsumoto, K. Morita, H.TAGAMI, T.SUZUKI, Y.TOBITA, Numerical study on sedimentation behavior of solid particles used as simulant fuel debris, Journal of Nuclear Science and Technology, 51, 5, 681-699, 2014.02.
22. S.CHENG, H.YAMANO, T.SUZUKI, Y.TOBITA, Y.Gondai, Y. Nakamura, B.ZHANG, Tatsuya Matsumoto, Koji Morita, Evaluation of Debris Bed Self-Leveling Behavior: A Simple Empirical Approach and its Validations, Annals of Nuclear Energy, 63, 188-198, 2014.01.
23. 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), ICONE21-15693, 2013.07.
24. S.CHENG, H.YAMANO, T.SUZUKI, Y.TOBITA, Y. Nakamura, B.ZHANG, Tatsuya Matsumoto, Koji Morita, Characteristics of Self-Leveling Behavior of Debris Beds in a Series of Experiments, Nuclear Engineering and Technology, 45, 3, 323-334, 2013.06.
25. Tatsuya MATSUMOTO, Yasunori KONO, Tetsushi HARADA, Daisuke HIRAHARA, Koji MORITA, Kenji FUKUDA, Transient Behavior of Particle Movement in a Boiling Debris Bed, Proc. of the Seventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7),October,2008, No.156, 2008.10.
26. Akihiro Uchibori, Tatsuya Matsumoto, Yorihisa Ishimaru, Masaya Yamashita, Ryo Akasaka, Koji Morita and Kenji Fukuda, INVESTIGATION INTO COOLABILITY BY TWO-PHASE FLOW IN NARROW FLOW PASSAGES, Proceedings of the 11th International Conference on Nuclear Engineering, ICONE11-36279, 2003.04.
27. Tatsuya Matsumoto, Akihiro Uchibori, Ryo Akasaka, Toshinori Seki, Shyuji Kaminishi, Koji Morita, and Kenji Fukuda, Applicability of Modified Drift Flux Model for Bubbly Flow in 2-D/3-D Rectangular Box With Various Kinds of Obstacles, Proceedings of the 10th International Conference on Nuclear Engineering, ICONE10-22245, 2002.04.
28. K. Fukuda, T. Matsumoto, N. Kamesako, A. Uchibori, R. Akasaka, K. Nakagawa, K. Morita, A. Hotta, Applicability of Modified Drift Flux Model for 3-D Channel Bubbly Flow with a Rod Inserted, Computational Technologies for Fluids/Thermal/Structural/Chemical Systems with Industrial Applications -2001-, PVP-Vol.424-1, pp.79-86, 2001.07.
29. T. Matsumoto, N. Kamesako, T. Seki, A. Uchibori, R. Akasaka, N. Fujimoto, K. Nakagawa, K. Morita, K. Fukuda, Analytical and Experimental Studies of Two Phase Flows in 2-D Rectangular Box with obstacles Inserted, Proc. NTHAS2, Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, pp.658-665, 2000.10.
30. Jian YU, Tatsuya MATSUMOTO and Shigeru KOYAMA, NUMERICAL SOLUTION FOR LAMINAR FILM CONDENSATION OF PURE REFRIGERANT ON A VERTICAL FINNED SURFACE, Proceedings of the 5th ASME/JSME Thermal Engineering Joint Conference, 6359.pdf, pp.1−8, 1999.03.
31. S. KOYAMA, J. YU and T. MATSUMOTO, Approximate Analysis for Laminar Film Condensation of Pure Refrigerant on Vertical Finned Surface, Enhanced Heat Transfer, 5, 3, 191-200, Vol.5, pp.191−200, 1998.01.
Presentations
1. 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.
2. 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.
3. 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.
4. 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.
5. 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.
6. 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.
7. 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.
8. 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.
9. 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.
10. 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.
11. 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.