肖瑶
发布时间：2018-11-29 10:19:04
 |
肖瑶 讲师
所在系所核科学与工程学院
办公电话021-34204081 通讯地址上海交通大学机械与动力工程学院A楼303室 电子邮件yxiao@sjtu.edu.cn 个人主页http://me.sjtu.edu.cn/teacher_directory1/2099.html |
教育背景
2009.09-2014.09 西安交通大学 核能科学与工程 博士
2012.09-2013.09 麻省理工学院 核能科学与工程 联培博士
2004.09-2008.07 西安交通大学 核工程与核技术 学士
2012.09-2013.09 麻省理工学院 核能科学与工程 联培博士
2004.09-2008.07 西安交通大学 核工程与核技术 学士
工作经历
2014.10-至今 上海交通大学 核科学与工程学院 讲师，博士生导师
出访及挂职经历
2012.09-2013.09 麻省理工学院 核能科学与工程 联培博士
研究方向
反应堆热工水力；
流动传热；
安全分析；
安全审评
科研项目
2019-2021 国家自然科学基金，稠密栅内气液两相流动相界面输运模型研究，负责人
2018-2020 核能开发科研项目，环形燃料组件水力学试验验证，负责人
2017-2019 国家科技重大专项，三门核电站噪声测试方法可靠性验证试验和现场噪声测量支持，负责人
2016-2017 中广核集团，燃料组件试制件考验试验研究，负责人
2016-2019 上海市扬帆计划，紧密栅内两相流流型及相界面浓度分布特性实验与理论研究，负责人
2015-2017 国家科技重大专项，自主化定型组件零部件水力试验，负责人
2015-2017 国家科技重大专项，干燥器声共振分析方法工程适用性验证试验，负责人
2014-2015 中广核集团，波形板干燥器流场CFD分析，负责人
2014-2016 启动基金，近临界压力流动传热特性实验与理论研究，负责人
2018-2020 核能开发科研项目，环形燃料组件水力学试验验证，负责人
2017-2019 国家科技重大专项，三门核电站噪声测试方法可靠性验证试验和现场噪声测量支持，负责人
2016-2017 中广核集团，燃料组件试制件考验试验研究，负责人
2016-2019 上海市扬帆计划，紧密栅内两相流流型及相界面浓度分布特性实验与理论研究，负责人
2015-2017 国家科技重大专项，自主化定型组件零部件水力试验，负责人
2015-2017 国家科技重大专项，干燥器声共振分析方法工程适用性验证试验，负责人
2014-2015 中广核集团，波形板干燥器流场CFD分析，负责人
2014-2016 启动基金，近临界压力流动传热特性实验与理论研究，负责人
代表性论文专著
[1] Y. Xiao, W. Zhao, H. Gu, X. Gao, Effects of branch length and chamfer on flow-induced acoustic resonance in closed side branches, Annals of Nuclear Energy, 121 (2018) 186-193.
[2] Y. Xiao, Z. Hu, S. Chen, H. Gu, Experimental investigation and prediction of post-dryout heat transfer for steam-water flow in helical coils, International Journal of Heat and Mass Transfer, 127 (2018) 515-525.
[3] Y. Xiao, J.S. Pan, H.Y. Gu, Numerical investigation of spacer effects on heat transfer of supercritical fluid flow in an annular channel, International Journal of Heat and Mass Transfer, 121 (2018) 343-353.
[4] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure, Annals of Nuclear Energy, 113 (2018) 409-419.
[5] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental study of two-phase frictional pressure drop of steam-water in helically coiled tubes with small coil diameters at high pressure, Applied Thermal Engineering, 132 (2018) 18-29.
[6] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental study on dryout characteristics of steam-water flow in vertical helical coils with small coil diameters, Nuclear Engineering and Design, 335 (2018) 303-313.
[7] 赵伟, 肖瑶, 顾汉洋, 圆形封闭旁支管流致声共振实验研究, 原子能科学技术, 52 (2018) 70-75.
[8] Y. Xiao, H. Gu, X. Gao, H. Zhang, W. Zhao, Flow visualization study of flow-induced acoustic resonance in closed side branches, Annals of Nuclear Energy, 120 (2018) 559-568.
[9] S. Chen, Z.X. Hu, Y. Xiao, H.Y. Gu, Experimental investigation of subcooled flow boiling heat transfer in helical coils, Nuclear Engineering and Design, 327 (2018) 187-197.
[10] 陈佳跃, 熊珍琴, 肖瑶, 顾汉洋, 垂直圆管内超临界R134a对流传热实验研究, 核动力工程, 37 (2016) 27-31.
[11] J. Ge, C.L. Wang, Y. Xiao, W.X. Tian, S.Z. Qiu, G.H. Su, D.L. Zhang, Y.W. Wu, Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology, Progress in Nuclear Energy, 91 (2016) 83-96.
[12] D.L. Zhang, A. Rineiski, C.L. Wang, Z.P. Guo, Y. Xiao, S.Z. Qiu, Development of a kinetic model for safety studies of liquid-fuel reactors, Progress in Nuclear Energy, 81 (2015) 104-112.
[13] Y. Xiao, L.W. Hu, S.Z. Qiu, D.L. Zhang, G.H. Su, W.X. Tian, Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor, Journal of Nuclear Engineering and Radiation Science, 1 (2015) 7.
[14] H.Y. Gu, Z.X. Hu, D. Liu, Y. Xiao, X. Cheng, Experimental studies on heat transfer to supercritical water in 2 x 2 rod bundle with two channels, Nuclear Engineering and Design, 291 (2015) 212-223.
[15] Y. Xiao, L.W. Hu, C. Forsberg, S.Z. Qiu, G.H. Su, K. Chen, N.X. Wang, Analysis of the Limiting Safety System Settings of a Fluoride Salt-Cooled High-Temperature Test Reactor, Nuclear Technology, 187 (2014) 221-234.
[16] C.L. Wang, Y. Xiao, J.J. Zhou, D.L. Zhang, S.Z. Qiu, G.H. Su, X.Z. Cai, N.X. Wang, W. Guo, Computational Fluid Dynamics Analysis of a Fluoride Salt-Cooled Pebble-Bed Test Reactor, Nuclear Science and Engineering, 178 (2014) 86-102.
[17] 郭张鹏, 张大林, 肖瑶, 秋穗正, 田文喜, 苏光辉, 物理-热工耦合计算方法在熔盐堆稳态分析中的应用, 原子能科学技术, 47 (2013) 2071-2076.
[18] 肖瑶, 巫英伟, 苏光辉, 秋穗正, 压水堆核电厂一回路仿真可视化研究, 原子能科学技术, 47 (2013) 962-968.
[19] Y. Xiao, Y.W. Wu, W.X. Tian, S.Z. Qiu, G.H. Su, Development of VTSAS 1.0 and application to an IPWR, Nuclear Engineering and Design, 261 (2013) 20-32.
[20] Z.P. Guo, D.L. Zhang, Y. Xiao, W.X. Tian, G.H. Su, S.Z. Qiu, Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor, Annals of Nuclear Energy, 53 (2013) 309-319.
[21] Y. Xiao, D.L. Zhang, Z.P. Guo, Y.W. Wu, W.X. Tian, G.H. Su, S.Z. Qiu, Numerical analysis for a molten salt reactor in the presence of localized perturbations, Progress in Nuclear Energy, 60 (2012) 61-72.
[2] Y. Xiao, Z. Hu, S. Chen, H. Gu, Experimental investigation and prediction of post-dryout heat transfer for steam-water flow in helical coils, International Journal of Heat and Mass Transfer, 127 (2018) 515-525.
[3] Y. Xiao, J.S. Pan, H.Y. Gu, Numerical investigation of spacer effects on heat transfer of supercritical fluid flow in an annular channel, International Journal of Heat and Mass Transfer, 121 (2018) 343-353.
[4] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure, Annals of Nuclear Energy, 113 (2018) 409-419.
[5] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental study of two-phase frictional pressure drop of steam-water in helically coiled tubes with small coil diameters at high pressure, Applied Thermal Engineering, 132 (2018) 18-29.
[6] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental study on dryout characteristics of steam-water flow in vertical helical coils with small coil diameters, Nuclear Engineering and Design, 335 (2018) 303-313.
[7] 赵伟, 肖瑶, 顾汉洋, 圆形封闭旁支管流致声共振实验研究, 原子能科学技术, 52 (2018) 70-75.
[8] Y. Xiao, H. Gu, X. Gao, H. Zhang, W. Zhao, Flow visualization study of flow-induced acoustic resonance in closed side branches, Annals of Nuclear Energy, 120 (2018) 559-568.
[9] S. Chen, Z.X. Hu, Y. Xiao, H.Y. Gu, Experimental investigation of subcooled flow boiling heat transfer in helical coils, Nuclear Engineering and Design, 327 (2018) 187-197.
[10] 陈佳跃, 熊珍琴, 肖瑶, 顾汉洋, 垂直圆管内超临界R134a对流传热实验研究, 核动力工程, 37 (2016) 27-31.
[11] J. Ge, C.L. Wang, Y. Xiao, W.X. Tian, S.Z. Qiu, G.H. Su, D.L. Zhang, Y.W. Wu, Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology, Progress in Nuclear Energy, 91 (2016) 83-96.
[12] D.L. Zhang, A. Rineiski, C.L. Wang, Z.P. Guo, Y. Xiao, S.Z. Qiu, Development of a kinetic model for safety studies of liquid-fuel reactors, Progress in Nuclear Energy, 81 (2015) 104-112.
[13] Y. Xiao, L.W. Hu, S.Z. Qiu, D.L. Zhang, G.H. Su, W.X. Tian, Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor, Journal of Nuclear Engineering and Radiation Science, 1 (2015) 7.
[14] H.Y. Gu, Z.X. Hu, D. Liu, Y. Xiao, X. Cheng, Experimental studies on heat transfer to supercritical water in 2 x 2 rod bundle with two channels, Nuclear Engineering and Design, 291 (2015) 212-223.
[15] Y. Xiao, L.W. Hu, C. Forsberg, S.Z. Qiu, G.H. Su, K. Chen, N.X. Wang, Analysis of the Limiting Safety System Settings of a Fluoride Salt-Cooled High-Temperature Test Reactor, Nuclear Technology, 187 (2014) 221-234.
[16] C.L. Wang, Y. Xiao, J.J. Zhou, D.L. Zhang, S.Z. Qiu, G.H. Su, X.Z. Cai, N.X. Wang, W. Guo, Computational Fluid Dynamics Analysis of a Fluoride Salt-Cooled Pebble-Bed Test Reactor, Nuclear Science and Engineering, 178 (2014) 86-102.
[17] 郭张鹏, 张大林, 肖瑶, 秋穗正, 田文喜, 苏光辉, 物理-热工耦合计算方法在熔盐堆稳态分析中的应用, 原子能科学技术, 47 (2013) 2071-2076.
[18] 肖瑶, 巫英伟, 苏光辉, 秋穗正, 压水堆核电厂一回路仿真可视化研究, 原子能科学技术, 47 (2013) 962-968.
[19] Y. Xiao, Y.W. Wu, W.X. Tian, S.Z. Qiu, G.H. Su, Development of VTSAS 1.0 and application to an IPWR, Nuclear Engineering and Design, 261 (2013) 20-32.
[20] Z.P. Guo, D.L. Zhang, Y. Xiao, W.X. Tian, G.H. Su, S.Z. Qiu, Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor, Annals of Nuclear Energy, 53 (2013) 309-319.
[21] Y. Xiao, D.L. Zhang, Z.P. Guo, Y.W. Wu, W.X. Tian, G.H. Su, S.Z. Qiu, Numerical analysis for a molten salt reactor in the presence of localized perturbations, Progress in Nuclear Energy, 60 (2012) 61-72.
教学工作
先进反应堆数值模拟，研究生，48学时/3学分
核反应堆热工水力，本科生，51学时/3学分
核反应堆物理，本科生，51学时/3学分
先进核能系统，本科生，32学时/2学分
核反应堆热工水力，本科生，51学时/3学分
核反应堆物理，本科生，51学时/3学分
先进核能系统，本科生，32学时/2学分
学术兼职
熔盐冷却球床堆堆芯安全分析软件[FRAC]V1.0 2014SR082141
2014 ICONE22 Best Poster，美国机械工程师协会（ASME）
2013 国家奖学金（博士研究生），中华人民共和国教育部
荣誉奖励
2016 上海市扬帆计划，上海市科学技术委员会2014 ICONE22 Best Poster，美国机械工程师协会（ASME）
2013 国家奖学金（博士研究生），中华人民共和国教育部
地址：中国·上海市闵行区东川路800号 200240
网址：：http://nsse.sjtu.edu.cn
电话：021-34205182 传真：021-34205182
上海交通大学核科学与工程学院版权所有 @2018