2001 - 2002 Study on Multi-dimensional Behaviors of Gas-Liquid Two-phase Flows in Fuel Subassembly of Nuclear Reactors
2001 - 2002 原子炉燃料集合体内の多次元気液二相流挙動に関する研究
1999 - 2001 相変化を伴う多成分多相流のモデル化手法の開発
2001 - Study on Severe Transients of Accelerator Driven Systems
2000 - 2000 原子炉燃料集合体内の多次元気液二相流挙動に関する研究
2000 - 加速器駆動システムの安全性評価に関する研究
1997 - 1999 INSTABILITY OF TWO PHASE FLOW IN A 3-D NATURAL CIRCULATION COOLED NUCLEAR REACTOR SYSTEM
1998 - 多次元多成分多相流の数値シミュレーションに関する研究
1998 - Study on Numerical Simulation of Multi-dimensional, Multi-component, Multi-phase Flows
多次元多相流の数値シミュレーション
加速器駆動システムの過酷事故解析に関する研究
多成分多相流における熱・物質移行現象に関する研究
Numerical Simulation of Multi-dimensional, Multi-phase Flows
Safety Analysis of Severe Transients in Accelerator Driven Systems
Study on Heat-and Mass-Transfer Phenomena in Multi-phase, Multi-component Flows
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Papers (201)：
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima. Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications. Journal of Nuclear Engineering and Radiation Science. 2023. 9. 4
Wei Liu, Kazuya Gotou, Tsutaya Matumoto, Koji Morita. Flow Characteristics in Rectangular Micro-Channels with High Aspect Ratios. Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19). 2022
Hidemasa Yamano, Koji Morita. Preliminary Application of Eutectic Reaction Model on Boron Carbide and Stainless Steel to Severe Accident Simulation of Sodium-Cooled Fast Reactors. Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19). 2022
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. Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19). 2022
M.A. RAFIQ AKAND, W. LIU, T. MATSUMOTO, K. MORITA. Mechanistic Critical Heat Flux Prediction for In-Vessel Retention Conditions. Nuclear Engineering and Design. 2021. 58. 384. 111494-111494
2018/10 - Technical Program Committee of NUTHOS-12 Best Paper Award of the 12th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-12)
2018/10 - Technical Program Committee of NUTHOS-12 Best Reviewer Award of the 12th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-12)
