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Xin Li
Xin Li
Waseda Research Institute for Science and Engineering, Waseda University
在 aoni.waseda.jp 的电子邮件经过验证
标题
引用次数
引用次数
年份
An accurate and stable multiphase moving particle semi‐implicit method based on a corrective matrix for all particle interaction models
G Duan, S Koshizuka, A Yamaji, B Chen, X Li, T Tamai
International Journal for Numerical Methods in Engineering 115 (10), 1287-1314, 2018
952018
Numerical simulation of the SURC-2 and SURC-4 MCCI experiments by MPS method
X Li, Y Oka
Annals of Nuclear Energy 73, 46-52, 2014
412014
A numerical study of isotropic and anisotropic ablation in MCCI by MPS method
X Li, A Yamaji
Progress in Nuclear Energy 90, 46-57, 2016
402016
Three-dimensional numerical study on the mechanism of anisotropic MCCI by improved MPS method
X Li, A Yamaji
Nuclear Engineering and Design 314, 207-216, 2017
242017
Development of MPS method for analyzing melt spreading behavior and MCCI in severe accidents
A Yamaji, X Li
Journal of Physics: Conference Series 739 (1), 012002, 2016
202016
Numerical simulation on single Taylor bubble rising in LBE using moving particle method
X Li, W Tian, R Chen, G Su, S Qiu
Nuclear Engineering and Design 256, 227-234, 2013
182013
Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3
N Takahashi, G Duan, A Yamaji, X Li, I Sato
Nuclear Engineering and Design 379, 111244, 2021
112021
Sensitivity analysis of in-vessel accident progression behavior in Fukushima Daiichi Nuclear Power Plant Unit 3
X Li, I Sato, A Yamaji
Annals of Nuclear Energy 133, 21-34, 2019
82019
2D MPS method analysis of ECOKATS-V1 spreading with crust fracture model
Y Umazume, N Takahashi, X Li, G Duan, A Yamaji
Nuclear Engineering and Design 379, 111251, 2021
52021
Analysis of the localized metallic phase solidification in VULCANO VF-U1 with MPS method
T Fukuda, A Yamaji, X Li, JF Haquet, A Boulin
Nuclear Engineering and Design 385, 111537, 2021
42021
Improvement of solidification model and analysis of 3D channel blockage with MPS method
R Kawakami, X Li, G Duan, A Yamaji, I Sato, T Suzuki
Frontiers in Energy 15 (4), 946-958, 2021
42021
Three-dimensional numerical study on pool stratification behavior in molten corium-concrete interaction (MCCI) with MPS method
X Li, I Sato, A Yamaji, G Duan
International Conference on Nuclear Engineering 51494, V06BT08A023, 2018
42018
Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2
M Regalado, X Li, A Yamaji, I Sato
Annals of Nuclear Energy 160, 108430, 2021
32021
Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident
X Li, I Sato, A Yamaji, M Regalado, J Wang
Annals of Nuclear Energy 150, 107819, 2021
32021
A new potential interface tension model for MPS method avoiding unphysical particle cohesion
T Fukuda, X Li, A Yamaji
Progress in Nuclear Energy 150, 104311, 2022
12022
Estimation of debris relocation and structure interaction in the pedestal of Fukushima Daiichi Nuclear Power Plant Unit-3 with Moving Particle Semi-implicit (MPS) method
X Li, A Yamaji, G Duan, I Sato, M Furuya, H Madokoro, Y Ohishi
Annals of Nuclear Energy 169, 108923, 2022
12022
Estimation of long-term ex-vessel debris cooling by water in fukushima Daiichi nuclear power plant unit-3
I Sato, A Yamaji, X Li, H Madokoro
International Conference on Nuclear Engineering 85260, V003T12A016, 2021
12021
Preliminary evaluation on the relocation phase of ex-vessel debris of fukushima daiichi nuclear power plant unit-3
X Li, A Yamaji, M Furuya, I Sato, H Madokoro, Y Ohishi
International Conference on Nuclear Engineering 85260, V003T12A027, 2021
12021
Sensitivity study of accident scenarios on MCCI for Fukushima Daiichi unit-1 by MELCOR
T Noju, A Yamaji, K Matsumoto, X Li
2017 International Congress on Advances in Nuclear Power Plants: A New …, 2017
12017
Numerical simulation of anisotropic ablation of siliceous concrete-Analysis of CCI-3 MCCI experiment by MPS method
X Li, A Yamaji
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2015
12015
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