Profile
Xu HAN
Postdoctoral Research Associate
Institute of Industrial Science
The University of Tokyo
Room: De202
TEL&FAX: +81-(0)3-5452-6171 (EXT: 56171)
E-mail: xu-han [at] iis.u-tokyo.ac.jp
Japansese page is here
Education
- Sep. 2011 - Jun. 2015
- B. Eng. in Nuclear Engineering, Harbin Engineering University, Harbin, China
- Sep. 2015 - Jun. 2018
- M. Eng. in Nuclear Engineering, Shanghai Jiao Tong University, Shanghai, China
- Oct. 2018 – Sep. 2021
- D. Eng., in Nuclear Engineering, Kyoto University, Kyoto, Japan
Research Interests
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Optimal design of thermo-fluid system
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Nuclear safety
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Gas-liquid two-phase flow
Publications (Research Articles)
X. Han, X. Shen, T. Yamamoto, K. Nakajima, H. Sun, T. Hibiki
“Flow regime and void fraction predictions in vertical rod bundle flow channels”
International Journal of Heat and Mass Transfer, 178, 121637 (2021)
X. Han, X. Shen, T. Yamamoto, K. Nakajima, T. Hibiki
“Drift-flux correlation for upward gas-liquid two-phase flow in vertical rod bundle flow channel”
International Journal of Heat and Mass Transfer, 162, 120341 (2020).
X. Han, X. Shen, T. Yamamoto, K. Nakajima, H. Sun, T. Hibiki
“Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6×6 rod bundle”
International Journal of Heat and Mass Transfer, 144, 118696 (2019).
X. Shen, T. Yamamoto, X. Han, T. Hibiki
“Interfacial area concentration in gas-liquid metal two-phase flow”
Experimental and Computational Multiphase Flow (in Press, https://doi.org/10.1007/s42757-021-0110-x.)
“Local measurements of upward air-water two-phase flows in a vertical 6×6 rod bundle”
Experimental and Computational Multiphase Flow, 1(3), 186-200 (2019).
Proceedings in English
X. Han, X. Shen, T. Yamamoto, K. Nakajima, T. Hibiki“Flow characteristics of upward two-phase flows in a rod bundle geometry”
Proceedings of ASME’s Power 2020 and Nuclear Engineering Conference powered by ICONE (International Conference on Nuclear Engineering), Paper No.: ICONE28-POWER2020-14568, Anaheim, California, USA, August, 2020. (Virtual Conference)
X. Han, J. Xiong, X. Cheng
“Benchmark of CFD methodology for boron dilution simulation based on ROCOM experiment”
Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Paper No.: 20750, Xi'an, China, September, 2017.
X. Han, J. Xiong, X. Cheng
“Numerical simulation of coolant mixing process during pressurized thermal shock in ROCOM facility”
Proceedings of ISSNP 2016 (the 8th International Symposium on Symbiotic Nuclear Power Systems for 21st Century), Paper No.: ISSNP 2016-050, Chengdu, China, September, 2016