1. Bian H, Sun Z, Ding M, Zhang N, Meng Z. Application and evaluation of automatic wall treatment on diffusion boundary layer based steam condensation model in presence of air[C]. International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi'an China, 2017. (EI: 20183605763835)
2. Bian H, Sun Z, Ding M, Zhang N, Yang Y, Tian W. A fluid film CFD model for steam condensation in presence of air[C]. International Conference on Nuclear Engineering, Charlotte, the USA, 2016. (SCI: 000387191000059)
3. Zhou J, Ding M, Bian H, Zhang Y, Sun Z. Improving the flow distribution in a Z-type heat exchanger having optimized tube structure, in: International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
4. 李龚霖, 边浩志, 孙建闯, 丁铭. 倾斜管束条件下含空气蒸气冷凝换热特性分析[C], 第十六届全国反应堆热工流体学术会议，惠州，2019.
5. 孙建闯, 曹夏昕, 边浩志, 成翔, 汪宇, 丁铭. 不凝性气体对低高差开式自然循环流动特性影响实验研究[C], 第十六届全国反应堆热工流体学术会议，惠州，2019.
6. Guo Z, Sun Z, Zhang N, Ding M, Bian H, Meng Z. DEM-CFD study on fluid flow through radial layered composite packed beds[C]. International Conference on Nuclear Engineering, London, England, 2018.
7. Zhou J, Ding M, Bian H, Zhang Y, Sun Z. Numerically investigation on the characteristic of the reverse flow phenomenon in a Z-type parallel compact heat exchanger with large number of tubes, International Conference on Nuclear Engineering[C]. International Conference on Nuclear Engineering, London, England, 2018.
8. Liu X, Li C, Bian H, Yan C, Ding M. Enhanced heat transfer and resistance performance of new complex twisted tapes for highly-viscous fluid flow inside tubes [C]. International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi'an, Shaanxi, China, Sep, 2017. (EI: 20183605771869).
9. Liu X, Ding M, Bian H, Yan C, Li C. Numerical study on heat transfer and resistance of a tube fitted with new twisted tapes for lubricating oil[C] International Conference on Nuclear Engineering, Shanghai, China, 2017. (SCI: 000426020900052)
10. Chen K, Yan C, Kurwitz C, Cheng K, Bian H. Experimental Study of Helix-Finned Surface for Nucleate Pool Boiling[C]. International Conference on Nuclear Engineering, Charlotte, the USA, 2016. (SCI: 000387191000003)
11. 程坤, C. Kurwitz, 谭思超, 边浩志, 陈凯伦. Inconel平板核态沸腾换热特性实验研究[C]. 第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会, 中国北京, 2015.