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 | 67 | 2019 |
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 | 59 | 2021 |
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 | 37 | 2021 |
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 | 28 | 2021 |
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 | 13 | 2020 |
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 | 7 | 2021 |
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 | 6 | 2022 |
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 | 3 | 2023 |
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 | 3 | 2021 |
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 | 3 | 2020 |
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 | 1 | 2022 |
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 | 1 | 2021 |
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 |