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连强 博士,助理研究员    

*个人简介:

连强,山西长治人,工学博士,助理研究员。20226月获得西安交通大学核科学与技术专业博士学位,目前从事先进核动力系统热工水力及安全分析、聚变堆包层结构设计及校核评价、并联通道流动不稳定性、反应堆系统分析程序及核热耦合等研究。在International Journal of Energy ResearchAnnals of Nuclear EnergyFusion Engineering and Design等国际知名SCI期刊上发表文章。


*教育经历:

2016/09-2022/06    西安交通大学       核科学与技术       博士学位

2012/09-2016/07    西安交通大学       核工程与核技术     学士学位


*研究方向:

[1]  先进核动力系统热工水力及安全分析

[2]  聚变堆包层结构设计及校核评价

[3]  并联通道流动不稳定性

[4]  反应堆系统分析程序及核热耦合


*科研项目:

 

*发表论文:

[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.

[9]  连强,刘镝,田文喜,秋穗正等.基于RELAP5的运动条件下并联双通道流动不稳定性研究[J].原子能科学技术, 2021, 52:875-880. (EI)

[10] 连强,田文喜,秋穗正等.基于RELAP5的螺旋管蒸汽发生器热工水力程序研发与验证[J],原子能科学技术, 2019, 53:1007-1013. (EI)