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SCI,EI及国内外会议共计发表61篇（截止2024.10-其中SCI论文23篇）；
1. Qi S, HanB*, Zhu X, et al. Machine learning in critical heat flux studies in nuclear systems: A detailed review[J]. Progress in Nuclear Energy, 2025, 179: 105535. (SCI) 2. Han B, Yang B W, Zhu X, et al. Liquid level monitoring and quenching front tracking for SMR rod bundle CHF tests under low pressure, low flow, high quality conditions[J]. Nuclear Engineering and Design, 2024, 427: 113426. (SCI) 3. Han B, Yin Y, Zhu X, Yang B W, et al. A subchannel analysis code for advanced Liquid Metal Fast Reactor Cores and Study on Heat Transfer Characteristics of Core Geometry Parameters [J]. Progress in Nuclear Energy, 2024. (SCI) 4. Han B, Yang B W, Zhu X, et al. Design and development of a spacer grids with minimum thermal–hydraulic impacts for rod bundle CHF testing with bowed or ballooned rods[J]. Nuclear Engineering and Design, 2024, 425: 113349. (SCI) 5. Han B, Zhu X, Yang B W, et al. Review of the representative development history on rod bundle mixing coefficient used in subchannel analysis code of PWR[J]. Progress in Nuclear Energy, 2024, 170: 105113.(SCI) 6. Han B, Yin Y, Yang B W, et al. Numerical study on the size effect on the mixing in 2× 1, 3× 3 and 5× 5 rod bundle subchannels[J]. Nuclear Engineering and Technology, 2024. (SCI) 7. Yin Y, HanB*, Zhu X, et al. Development of a liquid metal subchannel code applied to ocean conditions and study on the effect of core geometry parameters and ocean motions on flow and heat transfer characteristics[J]. Progress in Nuclear Energy, 2024, 177: 105469.(SCI) 8. Han, Bin, et al. Study on the mixing performance of mixing vane grids and mixing coefficient by CFD and subchannel analysis code in a 5× 5 rod bundle. Nuclear Engineering and Technology 55.10 (2023): 3775-3786. (SCI) 9. Han, Bin, et al. Numerical study on temperature distribution and mixing effect by spacer grid in 2× 1 subchannel. Annals of Nuclear Energy 181 (2023): 109531. (SCI) 10. Han B, Zhu X, Yang B W, et al. Verification and validation of CFD and its application in PWR fuel assembly[J]. Progress in Nuclear Energy, 2022, 154: 104485. (SCI) 11. Yang B W, Anglart H, HanB*, et al. Progress in rod bundle CHF in the past 40 years[J]. Nuclear Engineering and Design, 2021, 376: 111076. (SCI) 12. Yang B W, Han B*, Liu A, et al. Recent challenges in subchannel thermal-hydraulics-CFD modeling, subchannel analysis, CHF experiments, and CHF prediction[J]. Nuclear engineering and design, 2019, 354: 110236.（SCI） 13. Han B, Yang B W, Zha Y. Numerical study on the effect of grid mixing span in 2× 1 spacer grid [J]. Nuclear Engineering and Design, 2018, 339: 11-20. (SCI) 14. Han B, Yang B W, Wei C, et al. Study on the Lateral Velocity and Vortex in a Spacer Grid [J]. Nuclear Technology, 2018: 1-9. (SCI) 15. Han B, Yang B W, Zhang H, et al. The effect of spacer grid critical component on pressure drop under both single and two phase flow conditions [J]. Kerntechnik, 2016, 81(3):257-267. (SCI) 16. Han B, Yang B W, Zhang H, et al. Effects of axial power shapes on CHF locations in a single tube and in rod bundle assemblies [J]. Kerntechnik, 2016, 81(3):286-298. (SCI) 17. Liu A, Yang B W, Han B, et al.Turbulent Mixing Models and other Mixing Coefficients in Subchannel Codes-A Review Part A: Single Phase [J]. Nuclear Technology. 2020 (SCI) 18. Liu A, Yang B W, Han B, et al. Measurement uncertainty and quenching phenomena in uniform heating rod bundle CHF test [J]. Nuclear Engineering and Design, 2019, 348: 107-120. (SCI)) 19. Wei C, Yang B W, Han B, et al. The Impact of Mixing Vane Arrangement on Mixing Coefficient β for Subchannel Analysis[J]. Nuclear Technology, 2018: 1-10. (SCI) 20. Mao H, Yang B W, Han B, et al. Modeling of spacer grid mixing effects through mixing vane crossflow model in subchannel analysis[J]. Nuclear Engineering and Design, 2017, 320: 141-152. (SCI) 21. Mao H, Yang B W, Han B. Study on effects of mixing vane grids on coolant temperature distribution by subchannel analysis[J]. Kerntechnik, 2016, 81(3):244-250. (SCI) 22. Yang B W, Zhang H, Han B, et al. CFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies[J]. Kerntechnik, 2016, 81(3):221-232. (SCI) 23. Zhang B, Zhang H, Han B, et al. CFD evaluation on the thermohydraulic characteristics of tube support plates in steam generator[J]. Kerntechnik, 2016, 81(3):299-307. (SCI) 中文EI论文3篇； 24. 韩斌，杨保文*，张汇，查于东过冷沸腾工况下不同刚凸结构对定位格架热工水力性能影响的数值模拟分析[J]. 核动力工程, 2017, 38(3): 158-163. 25. 韩斌, 杨保文, 张汇, 等. 定位格架压降关系式及 CFD 数值模拟研究[J]. 核动力工程, 2017, 38(2): 169-174. 26. 杨保文, 韩斌,张汇, 等. 交混翼定位格架关键部件—交混翼角度/刚凸形状数值模拟研究[J]. 核动力工程, 2016, 37(2): 165-170. 国内外会议论文含一作，通讯作者及合作文章20多篇，部分被EI收录（未完全统计）； 27. Yin Y, Han B*, et al. Development of a Liquid Metal Subchannel Code Used in Ocean Conditions and Study the HeatTransfer Characteristics in Rod Bundle of Reactor Core[C],ICONE-31, August 4 - 8, 2024 at the Hilton Prague, Prague, Czech Republic(EI 收录) 28. Qi S, Han B*, et al. Understanding the Flow Anisotropic Turbulent Flow in the Subchannel of Fuel Assembly Under Effect of the Bare Rod and Mixing Vane Grid by LES[C],ICONE-31, August 4 - 8, 2024 at the Hilton Prague, Prague, Czech Republic(EI 收录) 29. Zhang Y Han B*, et al. Numerical Study on Subcooled Boiling and CHF Phenomenon in Eccentric Annular Channels[C], NUTHOS-14, Canada, 2024, 8 30. Han B, Zhu X*, et al. Study on the mixing vane grid effect on flow field and bubble distribution in a 2x1 subchannel by PIV and high speed camera [C]. NURETH-20, USA, 2023, 8(EI收录) 31. Han B, Zhu X*, et al. Effects of Numerical Geometry Features-wire rod contact and Working Fluids on Flow and Thermal Fields of Wire-Wrapped in a 7 Pin Bundles [C]. NUTHOS-13, Taiwan, 2022, 9. 32. Bin Han, Bao-Wen Yang* Cen Wei, Yudong Zha. CFD analysis on mixing vane grid performance in a 5×5 rod bundle [C]. The 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Portland, Oregon, USA. August 18-23, 2019. (EI收录) 33. Bin Han, Bao-Wen Yang*, Cen Wei, Yudong Zha. Effect of Indirect Heating of Rod Bundle in Fuel Assembly Thermal Hydraulic Experiment on Local Heat Flux Measurement [C]. The 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Portland, USA. August 18-23, 2019(EI收录) 34. Bin Han, Bao-Wen Yang* and Yudong Zha. Improvement of Subchannel Cross Flow Simulation Based on Mixing Matrix Obtained from CFD Modelling. [C] NUTHOS-12, October, 14-18 2018 Qingdao China 35. Bin Han, Bao-Wen Yang*, Cen Wei, Yudong Zha.CFD analysis on mixing vane grid performance in a 5×5 rod bundle [C] IS-ReCTHA, Aug. 29-31 2018 Lecco, Italy 36. Bin Han, Bao-Wen Yang, Cen Wei, et al.Void Fraction Distribution and Code-to-code Comparison of Subcooled Boiling in a 5X5 Rod Bundle.[C]// The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Xi’an, China. 2017. (EI收录) 37. Bao-Wen Yang, Cen Wei,Bin Han*, et al. COMPARISON OF THE EFFECTS OF DIFFERENT TYPES OF WELDING NUGGETS. [C]// The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Xi’an, China. 2017. (EI收录) 38. Bin Han, Bao-Wen Yang, Yudong Zha, Grid pressure drop prediction in a fuel assembly, American Nuclear Society annual meeting（ANS）, 2017，San Francisco, USA(EI收录) 39. Bin Han, Hui Zhang, Bao-wen Yang, Yudong Zha, Yuxiang Zhang. Numerical Study on Subcooled Boiling of Void Fraction Distribution in 5×5 Rod Bundle, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics(WORTH-7), 2015, Kunming, China 40. Cen wei, Bao-Wen Yang, Bin Han, Numerical Study of the Impact of the Fuel Rod Swelling on The Thermal Hydraulic Performance in 2X2 Rod Bundle. [C]// American Nuclear Society annual meeting（ANS）, 2018,Philadelphia , USA(EI收录) 41. Cen Wei, Bao-Wen Yang, Bin Han, Numerical study on the impact of the partially blocked rod bundle on the flow field. [C] IS-ReCTHA, Aug. 29-31 2018 Lecco, Italy 42. Hongmei Lyu, Bao-Wen Yang* and Bin Han. ROD-TO-WALL GAP CALCULATION THROUGH CFD MODELING. [C]// The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Xi’an, China. 2017. (EI收录) 43. Zhaobo Zhou, Bao-wen Yang*, Bin Han, et al. THE STUDY ON INTEGRATIVE EFFECT OF DIMPLE AND MIXING VANE ON SPACER GRID DESIGN.[C]// The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Xi’an, China. 2017. (EI收录) 44. Hongmei Lyu, Bao-Wen Yang*, Hu Mao and Bin Han. COMPARING SUBCHANNEL CODE AND CFD FOR THE ROD-TO-WALL GAP CALCULATION. [C]// The 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulic, Xi’an, China. 2017. (EI收录) 45. Hongmei Lyu, Bao-Wen Yang, Bin Han, Influence of Axial Power Distributions on Rod-to-wall Gap, American Nuclear Society annual meeting（ANS）, 2017，San Francisco, USA(EI收录) 46. Cen Wei, Bao-Wen Yang*, Bin Han, Comparison of mixing effect of spacer grids with different mixing vane angle[C]. 9th XJTU-UT-SJTU Joint International Symposium on Nuclear Science and Technology, Shanghai, China, Nov. 13-15, 2016 47. Hui Zhang, Bao-Wen Yang, Bin-Zhang, Bin Han*. ShaoJia Mo, HongBing Ren, JiaMing Qin, ChaoPing Zuo. Numerical Analysis On The Thermal Hydraulic Performance Of Steam Generator Support Plate In Subcooled Region, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics(WORTH-7), 2015, Kunming, China 48. Hui Zhang, Bao-Wen Yang, Bin Han*, YuDong Zha. CFD study on the cold wall effect of 5x5 spacer grid in subcooled boiling region, 13th Multiphase Flow Conference & Short Course, 2015, Dresden, Germany 49. Zhang H, Yang B W, Zhang B, Han B et al. Numerical Study on the Effects of Vane Angle and Dimple on The Thermal Hydraulic Performance of A PWR Fuel Assembly[C]//NURETH-16, Chicago, USA. 2015. (EI收录) 50. 张远杰，韩斌*等，螺旋十字燃料过冷沸腾及临界热流密度传热特性数值研究[C]. 第四届全国核反应堆热工流体力学学术年会，北京，2024.10 51. 齐思维，韩斌等*. 融入几何特征的数据驱动各向异性湍流模型[C]. 首届全国智能流体力学会议，西安，2024.10. 52. 宋铃平，韩斌*等. 液态金属铅基快堆堵流工况堆芯棒束通道热工水力特性研究[C]. 核反应堆技术全国重点实验室2024年学术年会, 成都，2024.4. 53. 宋铃平，韩斌*等. 非典型流道盒棒壁间距对铅冷快堆热工水力实验流动换热特性的影响[C]. 中国核学会核反应堆热工流体力学分会第三届学术年会暨中核核反应堆热工水力技术重点实验室年会, 西安，2023.9. 54. 宋铃平，韩斌*等. 铅冷快堆棒束实验支撑格架的热工水力[C]. 第十一届反应堆物理与核材料科学研讨会, 兰州，2023.8. 55. 尹园园，韩斌*等. 铅冷快堆子通道程序开发及绕丝强化换热特性研究[C]. 第十一届反应堆物理与核材料科学研讨会, 兰州，2023.8. 56. 韩斌，朱小良*等. 基于CFD的带绕丝7棒束和19棒束压力及流场特性的数值研究[C]. 中国核学会核反应堆热工流体力学年会, 哈尔滨，2022.12. 57. 韩斌，杨保文*, 吕红梅等, 定位格架2x1通道横流及涡流的数值研究[C].中核核反应堆热工水力技术重点实验室, 成都, 11.16-11.18,2016 58. 韩斌, 杨保文，魏岑. 燃料组件单相及两相格架压降预测. 第十五届全国反应堆热工流体学术会议, 山东荣成, 中国, 9月24-27日, 2017. 59. 魏岑，杨保文*，韩斌基于流固耦合方法的格架刚凸性能的数值模拟[C], 第十五届全国反应堆热工流体学术会议, 山东荣成, 中国, 9月24-27日, 2017. 60. 周兆波, 杨保文, 韩斌, 定位格架关键部件形阻系数的CFD研究[C]. 中核核反应堆热工水力技术重点实验室, 成都, 11.16-11.18,2016 61. 毛虎，杨保文，张汇，单建强，韩斌，单建强.新开发的子通道格架模型的验证[C]. 第十四届全国反应堆热工流体学术会议，北京，2015
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