Kyushu University Academic Staff Educational and Research Activities Database
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Koji Morita Last modified date:2018.06.11



Graduate School
Undergraduate School


E-Mail
Homepage
http://www.qpn.kyushu-u.ac.jp/lab6/
Nuclear Energy System Research Group, Department of Applied Quantum Physics and Nuclear Engineering .
Academic Degree
Doctor of Engineering
Country of degree conferring institution (Overseas)
No
Field of Specialization
Nuclear Engineering
Total Priod of education and research career in the foreign country
01years03months
Outline Activities
It is essential for utilization of safe and environment-friendly energy and public acceptance of nuclear energy to improve performance and safety of nuclear energy systems. For development of safe and reliable next-generation nuclear energy systems, it is required to accurate prediction of thermal-hydraulic phenomena such as momentum, heat and mass transfer in their design and safety assessment. For example, numerical simulation of complex multi-component, multi-phase flows in a reactor core is essential to investigate severe accidents of nuclear reactors. It is also required to predict multi-dimensional behaviors of two-phase flows in complex geometries such as fuel subassembly and steam generator. To solve engineering problems relevant to these subjects, research and educational activities are performed especially for the development of next-generation reactors such as fast breeder reactors and accelerator driven systems.
Research
Research Interests
  • Experimental Study on Thermal Hydraulics Phenomena of Multi-component, Multi-phase Flows
    keyword : Multi-phase Flow, Heat and Mass Transfer, Phase Change
    1998.11Title: Experimental Study on Thermal Hydraulics Phenomena of Multi-component, Multi-phase Flows: Event sequences of a core disruptive accident would strongly depend on thermal-hydraulic phenomena such as heat and mass transfer in the reactor core as well as neutron kinetics. In the present study, experimental investigation is conducted to understand key thermal-hydraulic phenomena of multi-component, multi-phase flows involved in core disruptive accidents..
  • Study on Numerical Simulation of Multi-dimensional, Multi-component, Multi-phase Flows
    keyword : Multi-phase Flow, Numerical Simulation, Heat and Mass Transfer
    1998.11Title: Study on Numerical Simulation of Multi-dimensional, Multi-component, Multi-phase Flows: It is one of important problems for more reliable reactor safety evaluation to improve numerical simulation techniques for involved thermal-hydraulic phenomena of multiphase, multicomponent flows in core disruptive accidents. In the present study, physical model development and experimental investigation are conducted to improve applicability of a fast-reactor safety analysis code for multiphase, multicomponent flows..
  • Study on Severe Transient Behaviors of Advanced Nuclear Reactors
    keyword : Fast Breeder Reactor, Accelerator Driven Systems, Reactor Safety, Severe Accident
    1998.11Title: Study on Severe Transeient Behaviors of Advanced Nuclear Reactors Reasonable prediction of consequences of even the most unlikely accident involving nuclear reactors needs detailed studies of posturated core disruptive accidents. In the present strudy, safety assessment technologies are developed for severe transeints of fast breeder reactors and accelerator driven systems..
Current and Past Project
  • R&D of Next Generation Methods for Fast Reactor Safety Analysis with Advanced Computational Science
  • A reserach project entitled 'Clarification of key thermal-hydraulic phenomena in severe transeint of accelerator driven systems' which forms part of the IAEA's Co-ordinated Research Project in 'Studies of advanced reactor technology options for effective incineration of radioactive waste'.
Academic Activities
Books
1. Introduction to Transport Phenomena.
Reports
1. H. Yamano, S. Fujita, Y. Tobita, K. Kamiyama, Sa. Kondo, K. Morita, M. Sugaya, M. Mizuno, S. Hosono, T. Kondo, SIMMER-IV: Three Dimensional Computer Program for LMFR Core Disruptive Accident Analysis -Version 2.A Model Summary and Program Description -, Japan Nuclear Cycle Development Institute, JNC TN9400 2003-070, 2003.08.
2. H. Yamano, S. Fujita, Y. Tobita, K. Kamiyama, Sa. Kondo, K. Morita, E. A. Fischer, D. J. Brear, N. Shirakawa, X. Cao, M. Sugaya, M. Mizuno, S. Hosono, T. Kondo, W. Maschek, E. Kiefhaber, G. Buckel, A. Rineiski, M. Flad, T. Suzuki, P. Coste, S. Pigny, J. L, SIMMER-III: A Computer Program for LMFR Core Disruptive Accident Analysis -Version 3.A Model Summary and Program Description -, Japan Nuclear Cycle Development Institute, JNC TN9400 2003-071, 2003.08.
3. K. Morita, H. Yamano, Y. Tobita, Sa. Kondo, SIMMER-III/IV Heat- and Mass-Transfer Model - Model and Method Description -, Japan Nuclear Cycle Development Institute, JNC TN9400 2003-047, 2003.07.
4. K. Morita, Y. Tobita, Sa. Kondo, E. A. Fischer, SIMMER-III Analytic Thermophysical Property Model, Japan Nuclear Cycle Development Institute, JNC TN9400 2000-004, 1999.05.
5. K. Morita, Y. Tobita, Sa. Kondo, E. A. Fischer, K. Thurnay, SIMMER-III Analytic Equation-of-State Model, Japan Nuclear Cycle Development Institute, JNC TN9400 2000-005, 1999.05.
Papers
1. Koji Morita, Tatsuya Matsumoto, Sinpei Nishi, Tatsuya Nishikido, Songbai Cheng, Hirotaka Tagami, Tohru Suzuki, Yoshiharu 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.
2. K. MORITA, S. ZHANG, S. KOSHIZUKA, Y. TOBITA, H. YAMANO, N. SHIRAKAWA, F. INOUE, H. YUGO, M. NAITOH, H. OKADA, Y. YAMAMOTO, M. HIMI, E. HIRANO, S. SHIMIZU, M. OUE, Detailed Analyses of Key Phenomena in Core Disruptive Accidents of Sodium-cooled Fast Reactors by the COMPASS Code, Nuclear Engineering and Design, 241, 12, 4672-4681, 2011.12.
3. B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Self-Leveling Onset Criteria in Debris Beds, J. Nuclear Science and Technology, 47, 4, 384-395, 2010.04.
4. M. Kabir HOSSAIN, Y. HIMURO, K. MORITA, K. NAKAGAWA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Simulation of Molten Metal Penetration and Freezing Behavior in a Seven-pin Bundle Experiment, J. Nuclear Science and Technology, Vol.46, No.8, pp.799-808, 2009.08.
5. S. ZHANG, S. KUWABARA, T. SUZUKI, Y. KAWANO, K. MORITA, K. FUKUDA, Simulation of Solid–fluid Mixture Flow Using Moving Particle Methods, J. Computational Physics, Vol.228, Issue 7, pp.2552-2565, 2009.04.
6. M. Mizanur RAHMAN, Yoshiyuki EGE, Koji MORITA, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHEK, Simulation of Molten Metal Freezing Behavior onto a Structure, Nuclear Engineering and Design, Vol.238, Issue 10, pp.2706-2717, 2008.10.
7. Koji MORITA, Tatsuya MATSUMOTO, Kenji FUKUDA, Yoshiharu TOBITA, Hidemasa YAMANO, Ikken SATO, Experimental Verification of the Fast Reactor Safety Analysis Code SIMMER-III for Transient Bubble Behavior with Condensation, Nuclear Engineering and Design, Vol.238, Issue 1, pp.49-56, 2008.01.
8. Ping LIU, Satoshi YASUNAKA, Tatsuya MATSUMOTO, Koji MORITA, Kenji FUKUDA, Hidemasa YAMANO, Yoshiharu TOBITA, Dynamic Behavior of a Solid Particle Bed in a Liquid Pool, SIMMER-III Code Verification, Nuclear Engineering and Design, Vol.237, No.5, pp.524-535, 2007.03.
9. Koji Morita, Wernar Maschek, Michael Flad, Yoshiharu Tobita, Hidemasa Yamano, Thermophysical Properties of Lead-bismuth Eutectic for Use in Reactor Safety Analysis, J. Nuclear Science and Technology, Vol.43, No. 5, pp.1-11, 2006.05.
10. Shuai Zhang, Koji Morita, Kenji Fukuda, Noriyuki Shirakawa, An Improved MPS Method for Numerical Simulations of Convective Heat Transfer Problems, Int. J. Numerical Methods in Fluids, Vol.51, No. 1, pp. 31-47, 2006.05.
11. Ping Liu, Satoshi Yasunaka, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Yoshiharu Tobita, Simulation of the Dynamic Behavior of the Solid Particle Bed in a Liquid Pool: Sensitivity of the Particle Jamming and Particle Viscosity Models, J. Nuclear Science and Technology, Vol.43, No. 2, pp.140-149, 2006.02.
12. K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo, Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification, Nuclear Engineering and Design, 10.1016/S0029-5493(02)00351-5, 220, 3, 224-239, Vol. 220, No. 3, pp. 224-239, 2003.01.
13. K. Morita, Sa. Kondo, Y. Tobita, D. J. Brear, SIMMER-III Applications to Fuel-Coolant Interactions, Nuclear Engineering and Design, Vol. 189, pp. 337-357, 1999.01.
14. K. Morita, E. A. Fischer, K. Thurnay, Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part II: Properties of Fast Reactor Materials, Nuclear Engineering and Design, Vol. 183, No. 3, pp. 193-211, 1998.01.
15. K. Morita, E. A. Fischer, Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part I: Analytic Equation-of-State Model, Nuclear Engineering and Design, Vol. 183, No. 3, pp. 177-191, 1998.01.
Works, Software and Database
1. .
Membership in Academic Society
  • The Japanese Society for Multiphase Flow
  • Atomic Energy Society of Japan
  • The Japan Society of Mechanical Engineers
Educational
Educational Activities
Classes in Graduate School of Engineering:
- Nuclear Safety Engineering,
- Multiphase Flow Science in Energy Engineering,
- Nuclear Fuel Cycle Experiment II,
- Research Project in Nuclear Energy System C,
- Nuclear Energy System Laboratory C,
- Independent Study and Seminar in Nuclear Energy System C,
- Colloquium on Nuclear Energy System C,
- International Environmental System Engineering 3, and
- International Environmental System Engineering 5

Classes in Undergraduate School of Engineering:
- Exercises in Fundamental Physics IB,
- Transport Phenomena,
- Thermodynamics,
- Introduction to Nuclear Reactor Engineering,
- Seminar of Applied Quantum Physics II and III,
- Engineering Analysis and Design, and
- Bachelor Research Work in Energy Science and Engineering
Other Educational Activities
  • 2013.12.
  • 2011.02.
  • 2009.11.