| 1. |
Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (11) Overview of project progress. |
| 2. |
Development of a passive safety shutdown device to prevent core damage accidents in fast reactors(13) Evaluations on core performance with candidate device specifications. |
| 3. |
Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (14) Evaluations on non-proliferation features of the passive shutdown device. |
| 4. |
Study on FPs removal effect on the containment vessel penetrations during a severe accident (3) Aerosol transport in parallel plate slit channels. |
| 5. |
Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (10) Selection of the device assembly design effective in the reactivity control by its material relocation. |
| 6. |
Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (7) Overview of overall project progress through FY2021. |
| 7. |
Study on FPs removal effect on the containment vessel penetrations during a severe accident (1) Development of an experimental method for FPs removal effect on the containment vessel penetrations reflecting actual plant conditions. |
| 8. |
Wei Liu, Kazuya Gotou, Tsutaya Matumoto and Koji Morita, Flow Characteristics in Rectangular Microchannels with High Aspect Ratios, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022.03. |
| 9. |
Ting ZHANG, Koji MORITA, Wei LIU, Xiaoxing LIU), Kenji KAMIYAMA, Numerical investigation on mechanism of heat transfer between molten pool and duct wall in EAGLE ID1 and ID2 in-pile tests, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022.03. |
| 10. |
Kazuya GOTO, Wei LIU, Tatsuya MATSUMOTO, Koji MORITA, FLOW CHARACTERISTICS IN RECTANULAR MICROCHANNELS, the Second Asian Conference on Thermal Sciences, 2021.10. |
| 11. |
Md. Abdur Rafiq Akand, Kei Kitahara, Tatsuya Matsumoto, Wei Liu, Koji Morita, A Modify Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling, 28th International Conference on Nuclear Engineering (ICONE28), 2021.08. |
| 12. |
Ting Zhang, Koji Morita, Xiaoxing Liu, Wei Liu, Kenji Kamiyama, A 3d Numerical Simulation on Heat Transfer Behavior in Eagle Id1 In-Pile Test Using Finite Volume Particle Method, 28th International Conference on Nuclear Engineering (ICONE28), 2021.08. |
| 13. |
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Koharu Kawase, Isamu Sato, Haruaki Matsuura T, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima, Development of a Passive Reactor Shutdown Device for Prevention of Core Disruptive Accidents in Fast Reactors: Project Overview and Preliminary Results, 28th International Conference on Nuclear Engineering (ICONE28), 2021.08. |
| 14. |
Ting Zhang, Koji Morita, Xiaoxing Liu, Wei Liu, Kenji Kamiyama, Particle-based simulation on heat transfer behavior between molten pool and duct wall in EAGLE ID1 and ID2 in-pile tests, ⽇本原⼦⼒学会2021年春の⼤会, 2021.03. |
| 15. |
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2020年春の⼤会, 2021.03. |
| 16. |
Md Abdur Rafiq Akand, Kei Kitahara, Tatsuya Matsumoto, Wei Liu, Koji Morita, Bubble Lift-off Size in Subcooled Flow Boiling for Inclined Heating Surface, 原子力学会2020秋の大会, 2020.09. |
| 17. |
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 (ATH'2020 topical meeting), 2020.07. |
| 18. |
M. A. Rafiq Akand, Tatsuya Matsumoto, Wei Liu and Koji Morita, Prediction of Bubble Departure Diameter for Downward Facing Heating Surface with Different Inclination Angle in IVR Condition, ⽇本原⼦⼒学会2020年春の⼤会, 2020.03. |
| 19. |
Seisuke Hosomi, Tomoyasu Akashi, Koji Morita, Wei Liu, Tsutaya Matsumoto, Kinuyoshi Takamatsu, Experimental study on heat removal performance of a new reactor cavity cooling system (RCCS), 11th Korea – Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2018.11. |
| 20. |
Masatsugu Kato, Kanji Funakoshi, Xiao Xing Liu, Tatsuya Matsumoto, Wei Liu and Koji Morita, Validation of a three-dimensional finite-volume-particle method for simulation of liquid-liquid mixing flow behavior, 11th Korea – Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2018.11. |
| 21. |
Le Hoang Sang PHAN, Yohei OHARA, Ry KAWATA, Xiaoxing LIU, Wei LIU, Koji MORITA, Liancheng GUO, Kenji KAMIYAMA, Hirotaka TAGAMI, Numerical Simulation on Self-leveling Behavior of Mixed Particle Beds Using Multi-fluid Model Coupled with DEM, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 2018.10. |
| 22. |
Koji MORITA, Ryusei OGAWA, Hiromi TOKIOKA, Xaoxing LIU, Wei LIU, Kenji KAMIYAMA, Particle-based Simulation of Heat Transfer Behavior in EAGLE ID1 In-pile Test, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 2018.10. |
| 23. |
Wei LIU 学生:0人, 学生以外:1人, Predictions of Critical Heat Flux for Subcooled Flow Boiling in Annulus, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 2018.10. |
| 24. |
Wei Liu 学生以外:1人, Prediction of transient surface temperature Changes at subcooled flow boiling DNB, 10th International Conference on Boiling and Condensation Heat Transfer, 2018.03. |
