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肖瑶    
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上海交通大学机械与动力工程学院A楼303室
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教育背景
时间
毕业院校
学历
2009/09-2014/09
西安交通大学 核能科学与工程
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
2012/09-2013/09..............麻省理工学院..核反应堆实验室..........联合培养博士研究生
出访及挂职经历
研究方向
反应堆热工水力;安全分析;流动传热;安全审评

课题组招生公告:课题组现招收硕士和博士研究生若干名,欢迎有志于从事反应堆热工水力相关领域研究的同学加入团队,有意者请发送个人简历到我的邮箱。
科研项目
2015-2016....................先进压水堆重大专项.....自主化定型组件零部件水力试验...............负责人
2015-2016....................先进压水堆重大专项.....干燥器声共振分析方法工程适用性验证试验.....负责人
2014-2015....................中国广核集团...........波形板干燥器流场CFD分析....................负责人
代表性论文专著
期刊论文:
[1] Y. Xiao, L. Hu, S. Qiu, D. Zhang, G. Su, W. Tian. Development of a Thermal-hydraulic Analysis Code and Transient Analysis for a FHTR[J]. Nuclear Engineering and Radiation Science, 2015, 1(1): 71–77.
[2] Y. Xiao, L. Hu, C. W. Forsberg, S. Qiu, G. Su, K. Chen, N. Wang. Analysis of the Limiting Safety System Settings of a Fluoride Salt Cooled High Temperature Test Reactor[J]. Nuclear Technology, 2014, 187(3): 221–234.
[3] Y. Xiao, Y. Wu, W. Tian, S. Qiu, G. Su. Development of VTSAS 1.0 and Application to an IPWR[J]. Nuclear Engineering and Design, 2013, 261(1): 20–32.
[4] Y. Xiao, D. Zhang, Z. Guo, Y. Wu, W. Tian, G. Su, S. Qiu. Numerical Analysis for a Molten Salt Reactor in the Presence of Localized Perturbations[J]. Progress in Nuclear Energy, 2012, 60(1): 61–72.
[5] H. Gua, Z. Hu, D. Liu, Y. Xiao, X. Cheng. Experimental Studies on Heat Transfer to Supercritical Water in 2×2 Rod Bundle with Two Channels[J]. Nuclear Engineering and Design, 2015, 291(1): 212–223.
[6] D. Zhang, A. Rineiski, C. Wang, Z. Guo, Y. Xiao, S. Qiu. Development of a Kinetic Model for Safety Studies of Liquid-fuel Reactors [J]. Progress in Nuclear Energy, 2015, 81(1):104–112.
[7] C. Wang, Y. Xiao, J. Zhou, D. Zhang, S. Qiu, G. Su, X. Cai, N. Wang, W. Guo. Computational Fluid Dynamics Analysis of a Fluoride Salt–Cooled Pebble-Bed Test Reactor[J]. Nuclear Science and Engineering, 2014, 178(1): 86–102.
[8] Z. Guo, D. Zhang, Y. Xiao, W. Tian, G. Su, S. Qiu. Simulations of Unprotected Loss of Heat Sink and Combination of Events Accidents for a Molten Salt Reactor[J]. Annals of Nuclear Energy, 2013, 53(1): 309–319.
[9] 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[J].原子能科学技术,2013, 47(6):962-968.
[10] 郭张鹏,张大林,肖瑶,田文喜,苏光辉,秋穗正.物理-热工耦合计算方法在熔盐堆稳态分析中的应用[J].原子能科学技术,2013,47(11):2071-2076.

会议论文:
[1] Y. Xiao, L. Hu, S. Qiu, D. Zhang, G. Su, W. Tian. Development of a Thermal-hydraulic Analysis Code and Transient Analysis for a FHTR[C]. 22nd International Conference on Nuclear Engineering (ICONE22), Prague, Czech Republic, July 7-11, 2014, No. 30615.
[2] Y. Xiao, L. Hu, C. W. Forsberg, S. Qiu, G. Su. Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor[C]. 21st International Conference on Nuclear Engineering (ICONE21), Chengdu, Sichuan, China, Jul. 29-Aug. 2, 2013, No. 16383.
[3] Y. Xiao, L. Hu, C. W. Forsberg, S. Qiu, G. Su. Effect of Salt Coolant Selection on FHTR Thermal Hydraulic Performance[C]. 2013 ANS Annual Meeting, Atlanta, GA, USA, Jun. 16-20, 2013, No. 7888.
[4] Y. Xiao, D. Zhang, Z. Guo, S. Qiu. Numerical Analysis for a Molten Salt Reactor in the Presence of Fissile Lump[C]. 20th International Conference on Nuclear Engineering (ICONE20), Anaheim, CA, USA, Jul. 30-Aug. 3, 2012, No. 54384.
[5] C. Wang, Y. Xiao, J. Zhou, D. Zhang, W. Tian, S. Qiu, G. Su. Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor with Different CFD Methods[C]. 22nd International Conference on Nuclear Engineering (ICONE22), Prague, Czech Republic, July 7-11, 2014, No. 30219.
[6] D. Zhang, Z. Zhai, A. Rineiski, Z. Guo, C. Wang, Y. Xiao, S. Qiu. COUPLE, a Time-dependent Coupled Neutronics and Thermal-hydraulics Code, and Its Applications to the MSFR and the CLEAR-I[C]. 22nd International Conference on Nuclear Engineering (ICONE22), Prague, Czech Republic, July 7-11, 2014, No. 30609.
[7] Z. Guo, Y. Xiao, J. Zhou, D. Zhang, K. S. Chaudri, S. Qiu. Coupled Neutronics/thermal-hydraulics for Analysis of Molten Salt Reactor[C]. 21st International Conference on Nuclear Engineering (ICONE21), Chengdu, Sichuan, China, Jul. 29-Aug. 2, 2013, No. 15012.
[8] Z. Guo, D. Zhang, Y. Xiao, S. Qiu. Development of Methodology for Analysis of Molten Salt Reactor[C]. 5th Joint International Symposium on Nuclear Science and Technology (5th XJTU-UT-SJTU Joint Workshop), Tokyo, Japan, August 20-21, 2012.
[9] 肖瑶,张大林,郭张鹏,秋穗正.新概念熔盐堆关键技术研究[C].全国新堆与研究堆第八届学术报告会,西安,2012年5月.
[10] 肖瑶,张大林,秋穗正.熔盐堆局部扰动数值分析计算[C].第二届“绿色能源、清洁动力”青年学者论坛,武汉,2011年10月.
[11] 秋穗正,肖瑶,王成龙,张大林,苏光辉.熔盐堆物理热工耦合及其热工安全特性研究[C].第一届新型反应堆安全及发展研讨会,兰州,2013年10月.
[12] 郭张鹏,张大林,肖瑶,秋穗正,田文喜,苏光辉.熔盐堆物理-热工水力耦合程序在堆芯稳态热工水力分析的研究[C].中核核反应堆热工水力技术重点实验室2012年度学术交流报告会,成都,2012年10月.
教学工作
先进反应堆数值模拟...........研究生................................51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
软件版权登记及专利
熔盐冷却球床堆堆芯安全分析软件[FRAC]V1.0...........................2014SR082141
学术兼职
荣誉奖励
2016/03......................上海市青年科技英才扬帆计划............上海市科学技术委员会
2014/07......................ICONE22.Best.Poster...................美国机械工程师协会(ASME)
2013/12......................国家奖学金(博士研究生)..............中华人民共和国教育部
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