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Wenbin Han
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GRID: a student project to monitor the transient gamma-ray sky in the multi-messenger astronomy era
J Wen, X Long, X Zheng, Y An, Z Cai, J Cang, Y Che, C Chen, L Chen, ...
Experimental Astronomy 48, 77-95, 2019
672019
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods
Y Ma, M Liu, B Xie, W Han, H Yu, S Huang, X Chai, Y Liu, Z Zhang
Annals of Nuclear Energy 151, 107923, 2021
592021
Coupled neutronic, thermal-mechanical and heat pipe analysis of a heat pipe cooled reactor
Y Ma, W Han, B Xie, H Yu, M Liu, X He, S Huang, Y Liu, X Chai
Nuclear Engineering and Design 384, 111473, 2021
372021
A flow rate measurement method for horizontal oil-gas-water three-phase flows based on Venturi meter, blind tee, and gamma-ray attenuation
Y Ma, C Li, Y Pan, Y Hao, S Huang, Y Cui, W Han
Flow Measurement and Instrumentation 80, 101965, 2021
282021
热管冷却反应堆核热力耦合研究
马誉高, 刘旻昀, 余红星, 黄善仿, 柴晓明, 谢碧衡, 韩文斌, 刘余, 杜政瑀, ...
核动力工程 41 (4), 191-196, 2020
132020
热管堆固态堆芯三维核热力耦合方法与分析
柴晓明, 马誉高, 韩文斌, 谢碧衡, 刘旻昀, 余红星, 黄善仿, 刘余, 杨韵佳, ...
原子能科学技术 55 (zengkan2), 189-195, 2021
72021
Neutronic and thermal-mechanical coupling schemes for heat pipe-cooled reactor designs
Y Ma, M Liu, B Xie, W Han, X Chai, S Huang, H Yu
Journal of Nuclear Engineering and Radiation Science 8 (2), 021303, 2022
62022
NTPSS-vPower: A model for system simulation of a nuclear thermal propulsion system
Z Qi, W Han, M Liu, C Ji, H Wei, S Huang
Annals of Nuclear Energy 192, 110019, 2023
32023
Coupled three-dimensional neutronic/thermal-mechanical analysis of heat pipe cooled reactor solid-state core
X CHAI, Y MA, W HAN, B XIE, M LIU, H YU, S HUANG, Y LIU, Y YANG, ...
Atomic Energy Science and Technology 55 (zengkan2), 189-195, 2021
32021
Neutronic/thermal-mechanical coupling in heat pipe cooled reactor
M Yugao, L Minyun, Y Hongxing, H Shanfang, C Xiaoming, X Biheng, ...
核动力工程 41 (4), 191-196, 2020
32020
Multi-physics Coupling Analyses of Nuclear Thermal Propulsion Reactor
W Han, Z Guan, S Huang, J Deng
International Confernece Pacific Basin Nuclear Conference, 941-954, 2022
12022
A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform
C Ji, B Xie, X Guo, W Han, Y Hao, J Chen, S Huang, K Wang, H Wei, ...
International Conference on Nuclear Engineering 85246, V001T01A005, 2021
12021
Modular gas-cooled reactor core optimal design and additive manufacturing performance based on SiC matrix dispersed with TRi-structural ISOtropic fuel
Q Lu, W Han, J Deng, H Li, Z Wei
Energy 308, 132837, 2024
2024
Direct Numerical Simulation Study on Turbulent Flow and Heat Transfer Behavior of Helium-Xenon Gas Mixture in a Round Pipe
R Zhang, J Deng, Z Wei, Q Lu, W Han
International Conference on Nuclear Engineering 88278, V007T08A018, 2024
2024
Generative Design of a Gas-Cooled Micro Reactor Based on Multi-Physics Analysis
W Han, Q Lu, J Deng, S Huang
International Conference on Nuclear Engineering 88247, V004T04A046, 2024
2024
Overview of the Application of Thermal Management in Industry and the Application Prospect in the DCS of the Nuclear Power Plant
Y Xu, J Deng, Z Qiu, D Zhu, D Wang, W Han
International Conference on Nuclear Engineering 88230, V003T03A008, 2024
2024
Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
W Han, J Deng, Q Lu, C Chen, Y Xu, T Zhang, S Huang
Journal of Nuclear Engineering and Radiation Science 9 (4), 041104, 2023
2023
超临界二氧化碳冷却反应堆空泡反应性研究.
刘旻昀, 崔容益, 赵星宇, 韩文斌, 黄善仿, 黄彦平
Atomic Energy Science & Technology 57 (9), 2023
2023
螺旋十字型燃料棒中子物理及热工水力性能分析
张涛, 韩文斌, 申鹏飞, 黄善仿, 王侃
核动力工程 44 (S1), 69-74, 2023
2023
Neutronic and Thermal-Hydraulic Analyses for an Additive Manufacturing Reactor Core With SiC Matrix and TRISO Particle Fuel
W Han, J Deng, Q Lu, C Chen, Y Xu, T Zhang, S Huang
International Conference on Nuclear Engineering 86502, V015T16A102, 2022
2022
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