LIAN Qiang

Biography:

Dr. LIAN Qiang is now an assistant research scientist at Department of Nuclear Engineering, Chongqing University. He works in nuclear thermal-hydraulics, including thermal-hydraulic and safety analysis of advanced nuclear power system, structure design and evaluation of blanket in fusion reactor, flow instability between parallel multi-channels, system code and neutronics/thermal-hydraulics coupling analysis. His work appears on International Journal of Energy Research、Annals of Nuclear Energy、Fusion Engineering and Design, among other peer-reviewed journals.

Education Background:

Xi’an Jiaotong University, Ph.D., School of Nuclear Science and Technology, 2016/09-2022/06

Xi’an Jiaotong University, B.S., School of Nuclear Science and Technology, 2012/09-2016/06

Research Interests:

[1] Thermal-hydraulic and safety analysis of advanced nuclear power system

[2] Structure design and evaluation of blanket in fusion reactor

[3] Flow instability between parallel multi-channels

[4] System code and neutronics/thermal-hydraulics coupling analysis

Selected Publications：

[1]  Lian Q, Cui SJ, Tian WX, et al. Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket[J]. Fusion Engineering and Design, 2017, 118:142-150. (SCI, EI)

[2]  Lian Q, Tian WX, Cui SJ, et al. Preliminary safety assessment on two LOCAs under ITER-like condition for the optimized CFETR helium cooled solid breeder blanket[J]. Fusion Engineering and Design, 2017, 121:235-244. (SCI, EI)

[3]  Lian Q, Tian WX, Qiu SZ, et al. Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels[J]. Annals of Nuclear Energy, 2018, 122:241-255. (SCI, EI)

[4]  Lian Q, Tian WX, Gao XL, et al. Study of flow instability in parallel channel system for water cooled blanket[J]. Fusion Engineering and Design, 2019, 148:111291. (SCI, EI)

[5]  Lian Q, Tian WX, Qiu SZ, et al. Neutronics influence of poloidal nonuniform neutron wall loading on helium-cooled ceramic breeder blanket for CFETR[J]. Fusion Engineering and Design, 2020, 161:111950. (SCI, EI)

[6]  Lian Q, Tian WX, Gao XL, et al. Code improvement, separate-effect validation, and benchmark calculation for thermal-hydraulic analysis of helical coil once-through steam generator[J]. Annals of Nuclear Energy, 2020, 141:107-333. (SCI, EI)

[7]  Tian WX, Lian Q, Qiu SZ, et al. Research of two-phase density wave instability in reactor core channels with rolling motion[J]. International Journal of Energy Research, 2020, 44:7323-7341. (SCI, EI)

[8]  Lian Q, Tian WX, Qiu SZ, et al. Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket[J]. International Journal of Advanced Nuclear Reactor Design and Technology, 2021, 3:154-165.