| 1. |
Hidemasa Yamano, Koji Morita, Preliminary Analysis of Severe Accident in Sodium-Cooled Fast Reactor Using Eutectic Reaction Model of Boron-Carbide Control-Rod Material, 20th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), 2023.08. |
| 2. |
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: (1) Safety Analysis of Device-loaded Cores with Different Fuel Materials, The 30th International Conference on Nuclear Engineering (ICONE30), 2023.05. |
| 3. |
Hiroshi Sagara, Masatoshi Kawashima, Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Yoshihiro Sekio, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: (2) A study on Selecting Candidate Fuel Materials for the Basic Device Specifications, The 30th International Conference on Nuclear Engineering (ICONE30), 2023.05. |
| 4. |
Md. Iqbal Hosan, Mizuki Koga, Akihiro Kakoi, Koji Morita, W. LIU, Xu Cheng, Experimental Study on Accident Source Terms Transport and Deposition Behavior in Nuclear Power Plants, The 30th International Conference on Nuclear Engineering (ICONE30), 2023.05. |
| 5. |
Ting Zhang, Yao Yao, Koji Morita, Xiaoxing Liu, Wei Liu, Yuya Imaizumi, Kenji Kamiyama, A Large-Scale Particle-Based Simulation of Heat And Mass Transfer Behavior in EAGLE ID1 In-Pile Test, The 30th International Conference on Nuclear Engineering (ICONE30), 2023.05. |
| 6. |
Zeren Zou, Koji Morita, Wei Liu, Development of a Simplified One-Dimensional CDA Bubble Model for Source Term Evaluation, The 30th International Conference on Nuclear Engineering (ICONE30), 2023.05. |
| 7. |
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima, Development of a Passive Safety Shutdown Device to Prevent Core Damage Accidents in Fast Reactors (1) Current Status of Overall Project Progress, International Symposium on Zero-Carbon Energy Systems, 2023.01. |
| 8. |
Hiroshi Sagara, Masatoshi Kawashima, Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Development of a Passive Safety Shutdown Device to Prevent Core Damage Accidents in Fast Reactors (2) Performance of the Device in Reactivity Control and Nuclear Material Management, International Symposium on Zero-Carbon Energy Systems, 2023.01. |
| 9. |
D. TAKATSUKA, K. MORITA, W. LIU, T. ZHANG, T. NAKAMURA, K. KAMIYAMA, Particle-Based Simulation of Jet Impingement Behaviors, The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12), 2022.11. |
| 10. |
M. KOGA, K. TAKANISHI, T. MATSUMOTO, W. LIU, K. MORITA, K. NAKAMUR, T. KANAI, Experimental Study on Aerosol Migration Behavior in Rectangular Penetrations, The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12), 2022.11. |
| 11. |
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device, The 2022 29th International Conference on Nuclear Engineering (ICONE29), 2022.08. |
| 12. |
古賀 瑞樹， 宇和田 尚悟, 劉 維, 守田 幸路, 中村 康一, 金井 大造, シビアアクシデント時の格納容器貫通部における核分裂生成物の除去効果に関する研究 (2)矩形貫通部におけるエアロゾル移行挙動に関する実験的研究, 日本原子力学会「2022年春の年会」, 2022.03. |
| 13. |
中村 康一, 金井 大造, 宇井 淳, 西村 聡, 西 義久, 劉 維, 守田 幸路, シビアアクシデント時の格納容器貫通部における核分裂生成物の除去効果に関する研究 (1) 実機条件を反映した格納容器貫通部FP除去試験手法の構築, 日本原子力学会「2022年春の年会」, 2022.03. |
| 14. |
園田 大貴, 石津 朋子, 守田 幸路, FP移行挙動に着目した高速炉炉心損傷挙動解析コードASTERIA-SFRによるFAUST試験解析, 日本原子力学会「2022年春の年会」, 2022.03. |
| 15. |
藤田 哲史, 石津 朋子, 守田 幸路, 溶融燃料プールのスロッシング運動に伴う即発臨界挙動, 日本原子力学会「2022年春の年会」, 2022.03. |
| 16. |
王 浩キン, 佐藤 勇, 守田 幸路, 受動的炉停止デバイスにおける模擬燃料合金材料の物性評価, 日本原子力学会「2022年春の年会」, 2022.03. |
| 17. |
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. |
| 18. |
Wei Liu, Kazuya Gotou, Tsutaya Matumoto, Koji Morita, Flow Characteristics in Rectangular Micro-Channels with High Aspect Ratios, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 2022.03. |
| 19. |
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, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 2022.03. |
| 20. |
Ting Zhang, Koji Morita, Xiaoxing Liu, Wei Liu, Kenji Kamiyama, A 3D Particle-Based Analysis of Molten Pool-to-Structural Wall Heat Transfer in a Simulated Fuel Subassembly, The Second Asian Conference on Thermal Sciences (2nd ACTS), 2021.10. |
| 21. |
TING ZHANG, KOJI MORITA, XIAOXING LIU, WEI LIU, KENJI KAMIYAMA, A 3D Numerical Simulation On Heat Transfer Behavior in EAGLE ID11 In-Pile Test Using Finite Volume Particle Method, The 28th International Conference on Nuclear Engineering (ICONE 2021), 2021.08. |
| 22. |
MD. ADUR RAFIQ AKAND, KOJI MORITA, WEI LIU, TATSUYA MATSUMOTO, A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling, The 28th International Conference on Nuclear Engineering (ICONE 2021), 2021.08. |
| 23. |
HIDEMASA YAMANO, TOSHIHIDE TAKAI, TOMOHIRO FURUKAWA, SHIN KIKUCHI, YUKI EMURA, KENJI KAMIYAMA, HIROYUKI FUKUYAMA, HIDEO HIGASHI, TSUYOSHI NISHI, HIROMICHI OHTA, KOJI MORITA, KINYA NAKAMURA, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019, The 28th International Conference on Nuclear Engineering (ICONE 2021), 2021.08. |
| 24. |
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. |
| 25. |
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年春の年会」, 2021.03. |
| 26. |
M.A. RAFIQ AKAND, T. MATSUMOTO, W. LIU, 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 '20), 2020.10. |
| 27. |
Md Abdur Rafiq Akand1, 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年秋の年会」, 2020.09. |
| 28. |
X. LIU, K. MORITA, H. YAMANO, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (4) Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide, ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE, 2020.08. |
| 29. |
H. YAMANO, T. TAKAI, T. FURUKAWA, S. KIKUCHI, Y. EMURA, K. KAMIYAMA, H. FUKUYAMA, H. HIGASHI, T. NISHI, H. OHTA, X. LIU, K. MORITA, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2018, ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE, 2020.08. |
| 30. |
Koji Morita, Tatsuya Matsumoto, Isao Tatewaki, Syo Fuchita, Sloshing of Molten Fuel Pool and the Recriticality - Reactivity insertion caused by fuel motion -, A Topical Expert Meeting on Re-criticality Free SFR Concepts during HCDA, 2016.10. |
| 31. |
GUO LIANCHENG, Morita Koji, Tagami Hirotaka, Tobita Yoshiharu, 3D Numerical Simulation of a Self-leveling Experiment using CFD-DEM Code, 日本原子力学会「2014年春の年会」, 2014.03. |
| 32. |
Liu XianXing, GUO LIANCHENG, Morita Koji, Development of a Hybrid Particle-Mesh Method for Multiphase Flow Simulations, 日本原子力学会「2014年春の年会」, 2014.03. |
| 33. |
Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita, 炉心損傷時の炉心物質再配置挙動評価手法の開発;(6) Analysis of self-leveling experiment using CFD-DEM code, 日本原子力学会「2013年秋の大会」, 2013.09. |
| 34. |
GUO LIANCHENG, Morita Koji, Tagami Hirotaka, Tobita Yoshiharu, Numerical Simulation of Bubbling Fluidized Bed using a CFD-DEM Hybrid Code, 日本原子力学会「2013年春の年会」, 2013.03. |
| 35. |
. |
