Kyushu University Academic Staff Educational and Research Activities Database
List of Papers
Wei Liu Last modified date:2021.06.19

Associate Professor / 原子力エネルギーシステム / Department of Applied Quantum Physics and Nuclear Engineering / Faculty of Engineering


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, https://doi.org/10.1016/j.anucene.2020.107867, 151, p.107867_1 --p.107867_11, 2021.02.
2. T. Zhang, K. Funakoshi, X. Liu, W. Liu, K. Morita, K. Kamiyama, Numerical Simulation of Heat Transfer Behavior in EAGLE ID1 In-Pile Test Using Finite Volume Particle Method, Ann. Nucl. Energy, https://doi.org/10.1016/j.anucene.2020.107856, 150, 107856, 2021.01.
3. 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), 32842, 2020.07.
4. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita, Comparative Methodology between Actual RCCS and Downscaled Heat-Removal Test Facility, Annals of Nuclear Energy, 133, 11, 830-836, vol. 133, pp 830-836 (November 2019)., 2019.11.
5. Le Hoang Sang Phan, Phi Manh Ngo, Ryo Miura, Yusuke Tasaki, Tatsuya Matsumoto, Wei Liu & Koji Morita , Self-leveling behavior of mixed solid particles in a cylindrical bed using a gas-injection method
, Journal of Nuclear Science and Technology, 56, 1, 111-122, 2019.01.
6. 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
, Proceedings of 11th Korea – Japan Symposium on Nuclear Thermal Hydraulics and Safety , No. 0142, 2018.11.
7. 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), Proceedings of 11th Korea –Japan Symposium on Nuclear Thermal Hydraulics and Safety, No.0144, 2018.11.
8. Wei Liu, Predictions of Critical Heat Flux for Subcooled Flow Boiling in Annulus, Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), No.1148, 2018.10.
9. 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, Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), No.954, 2018.10.
10. Wei Liu, Prediction of Transient Surface Temperature Changes at Subcooled Flow Boiling DNB, the 10th International Conference on Boiling and Condensation Heat Transfer, A360, 2018.03.