熊进标 副教授
所在系所核科学与工程学院
办公电话
通讯地址上海交大机械与动力工程学院A楼333室
电子邮件xiongjinbiao@sjtu.edu.cn
个人主页http://nsse.sjtu.edu.cn/School/html/jiaoshigerenxinxi/201207/18-1539.html


教育背景 2008-2011，东京大学 系统创新专业，博士
2005-2008，上海交通大学 核科学与工程专业，硕士
2001-2005，西安交通大学 核工程与核技术专业，学士

工作经历 2011年9月-2014年12月 上海交通大学 机械与动力工程学院 核科学与工程学院 讲师
2015年1月-现在 上海交通大学 机械与动力工程学院 核科学与工程学院 副教授

研究方向 先进核能系统基础热工水力问题；
单相及两相流动传热的直接数值模拟；
单相流场激光可视化测量；
两相流场及温场的可视化测量；
先进两相流试验方法。

科研项目 2018-2020，国家重点实验室基金：熔池行为数值模拟的MPS基础模型研究，课题负责人；
2017-2020，国家自然科学基金面上项目：耐事故核燃料碳化硅包壳表面腐蚀形貌对沸腾传热性能影响的机理研究，课题负责人；
2017-2020, 科技部大型先进压水堆核电站重大专项课题：全子通道截面单相可视化及过渡沸腾实验研究，课题负责人；
2017-2020，核能开发项目：燃料组件堆外转运中换热特性试验研究，课题负责人
2016-2019，科技部大型先进压水堆核电站重大专项课题：严重事故熔融物与水相互作用3D分析程序的确认和模型评估，课题负责人；
2016-2017，国家重点实验室基金：基于PIV方法的棒束通道流场测量研究，课题负责人；
2014-2015，国家重点实验室基金：棒束流动的激光多普勒测速及湍流模拟研究，课题负责人；
2014-2015，教育部留学回国人员基金：T形管内热搅混的实验与数值研究，课题负责人；
2013-2015，上海市浦江人才计划项目：基于折射率补偿激光测量的棒束流动研究，课题负责人；
2013-2014，国际原子能机构协调研究计划课题：Verification and Validation of CFD Code in Single-Phase Bundle Flows，课题负责人；
2012-2015，国家自然科学基金项目：基于超临界流体传热弱化机理的湍流模型开发，课题负责人；
2012-2012，日本东京大学合作研究课题： Study of Secondary Flow Effect for Flow-Accelerated Corrosion in Nuclear Power Plants, 课题负责人；
2011-2015，科技部大型先进压水堆核电站重大专项：核电软件课题之棒束内流动传热行为试验与验证研究, 课题负责人；
2011-2015，大型先进压水堆核电站重大专项三维熔融物-水相互作用分析程序开发子课题, 技术负责人；
2011-2014，核能开发项目：堆内超临界辐照实验回路设计技术研究，主要技术骨干；

代表性论文专著 SCI期刊文章
1)D. Jin, J. Xiong(*), X. Cheng. Investigation on interphase force modeling for vertical and inclined upward adiabatic bubbly flow, Nuclear Engineering and Design 350, 43-57 (2019).
2)T. Zhang, J. Xiong(*), et al. Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors, Annals of Nuclear Energy 131, 210-220 (2019).
3)X. Chai, X. Liu, J. Xiong, et al. Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle, Progress in Nuclear Energy, Article 103044 (2019).
4)X. Chai, X. Liu, J. Xiong, et al. CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle, Nuclear Engineering and Design 344, 107-121 (2019).
5)W. Qu, J. Xiong(*), S. Chen, X. Cheng. High-fidelity PIV measurement of cross flow in 5?×?5 rod bundle with mixing vane grids, Nuclear Engineering and Design 344, 131-143 (2019).
6)Z. Wang, J. Xiong(*), W. Yao, W. Qu, Y. Yang, Experimental investigation on the Leidenfrost phenomenon of droplet impact on heated silicon carbide surfaces, International Journal of Heat and Mass Transfer 128, 1206-1217 (2019).
7)W. Qu, J. Xiong(*), S. Chen, et al. PIV measurement of turbulent flow downstream of mixing vane spacer grid in 5×5 rod bundle, Annals of Nuclear Energy 132, 277-287 (2019).
8)J. Xiong, W. Qu, Z. Wu, X. Cheng. PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction, Annals of Nuclear Energy 120, 540-545 (2018).
9)J. Xiong, R. Cheng, et al. CFD simulation of swirling flow induced by twist vanes in a rod bundle, Nuclear Engineering and Design 338, 52-62 (2018).
10)J. Xiong, X. Cheng, Y. Yang, Numerical analysis on supercritical water heat transfer in a 2×2 rod bundle, Annals of Nuclear Energy, 80, 123-135 (2015).
11)J. Xiong, et al., Experimental investigation on anisotropic turbulent flow in a 6×6 rod bundle with LDV. Nuclear Engineering and Design 278, 333-343 (2014).
12)J. Xiong, X. Cheng. Turbulence modelling for supercritical pressure heat transfer in upward tube flow. Nuclear Engineering and Design 270, 249-258 (2014).
13)J. Xiong, et al.. Laser Doppler measurement and CFD validation in 3x3 bundle flow. Nuclear Engineering and Design 270, 396-403 (2014).
14)J. Xiong, X. Cheng, Y. Yang, Numerical investigation on mass transfer enhancement downstream of an orifice. International Journal of Heat and Mass Transfer 68, 366-374 (2014).
15)J. Xiong, S. Koshizuka, M. Sakai and H. Ohshima, Investigation on Droplet Impingement Erosion during Steam Generator Tube Failure Accident, Nuclear Engineering and Design, 249, 132-139 (2012).
16)M. Sakai, Y. Shigeto, X. Sun, T. Aoki, T. Saito, J. Xiong, S. Koshizuka. Lagrangian-Lagrangian modeling for a solid-liquid flow in a cylindrical tank. [J]. Chemical Engineering Journal, V200-202: 663–672 (2012).
17)J. Xiong, S. Koshizuka and M. Sakai, Turbulence Modeling for Mass Transfer Enhancement by Separation and Reattachment with Two-Equation Eddy-Viscosity Models, Nuclear Engineering and Design, 241(8), 3190-3200 (2011)
18)J. Xiong, S. Koshizuka, M. Sakai, Investigation on Droplet Impingement onto Wet Walls Based on Simulation Using Particle Method, Journal of Nuclear Science and Technology, 48(1), 145-153, (2011)
19)H. Okada, S. Uchida, M. Naitoh, J. Xiong, S. Koshizuka, Evaluation Method for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (V) Flow Accelerated Corrosion under Single- and Two-Phase Flow Conditions, Journal of Nuclear Science and Technology, 48(1), 65-75, 2011.
20)J. Xiong, S. Koshizuka, M. Sakai, Numerical Analysis of Droplet Impingement Using the Moving Particle Semi-implicit Method, Journal of Nuclear Science and Technology, 47(3), 314-321, 2010.
21)J.Xiong, Y.Yang, X.Cheng, CFD Application to Hydrogen Risk Analysis and PAR Qualification, Science and Technology of Nuclear Installations, Vol. 2009, Article ID 213981, 2009.
会议文章
1)J. Xiong, H. Wang, X. Cheng, Y. Yang. Numerical Simulation on Melting and Solidification Based on Lagrangian Approach. The 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, U.S., 2016. pp. NURETH16-13685.
2)J. Xiong, X. Cheng. CFD analysis on supercritical pressure water heat transfer in a 2x2 rod bundle, The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS10), Okinawa, Japan, December 14-18, 2014. pp. NUTHOS10-1041.
3)J. Xiong, Y. Yu, X. Cheng. Three-Dimensional LDV Measurement of Turbulent Flow in a 6x6 Rod Bundle, Proceeding of CFD4NRS5 OECD/NEA&IAEA Workshop: Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation, Zurich, Switzerland. September 2014.
4)M. Zhong, M. Lin, J. Xiong, Y. Li, Y. Yang. Numerical simulation of thermal behavior of a molten droplet covered with vapor film, Proceeding of ICONE22, Prague, Czech Republic, 2014. pp. 30293.
5)J. Xiong, X. Cheng, Y. Yang. Turbulence Modeling for Supercritical Fluid Heat Transfer in a Round Tube[C]. The 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Pisa, Italy, 2013.
6)J. Xiong, X. Cheng. Improvement of Turbulence Models for Prediction of Supercritical Pressure Heat Transfer[C]. The 6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6), Shenzhen, China, 2013.
7)Y. Yu, J. Xiong, X. Cheng. 3D Laser Doppler Measurement on turbulent flows in a 3x3 rod bundle[C]. International seminar on Subchannel Analysis, CFD modeling and verification (ISACC), Xi’an, China,2013.
8)H. Wang, J. Xiong, X. Cheng. Evaluation of Turbulence Model Performance in Predicting 3x3 Bundle Flows [C]. International seminar on Subchannel Analysis, CFD modeling and verification (ISACC), Xian, China, 2013.
9)J. Xiong, X. Pan, S. Koshizuka, L. Zhang, X. Cheng, CFD analysis on localized mass transfer enhancement in the downstream of an orifice. CFD4NRS-4: The Experimental Validation and Application of CFD and CMFD Codes in Nuclear Reactor Technology. Daejeon, Korea. September 10-12, 2012.
10)J. Xiong, X. Cheng, Y. Yang. CFD Modeling of mass transfer in the flow through an orifice with ζ-f model. In Proceedings of the 2012 20th International Conference on Nuclear Engineering collocated with the ASME 2012 Power Conference (ICONE20-POWER2012), Anaheim, California, USA, July 30 - August 3, 2011.
11)J. Xiong, S. Koshizuka, M. Sakai, H. Ohshima, Investigation on Sodium Droplet Impingement Phenomenon during Steam Generator Tube Failure Using MPS Method, 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), Oct. 2010, Shanghai, China.
12)J. Xiong, S. Koshizuka, M. Sakai, Correlations for LDI wall thinning rate based on the stress load, 2010 Fall Meeting of Atomic Energy Society of Japan, Sept., 2010, Sapporo, Japan.
13)J. Xiong, S. Koshizuka, M. Sakai, Parametric Investigation on the Mechanical Loads Induced by Liquid Droplet Impingement onto a Rigid Wall, 2010 International Congress on Advances in Nuclear Power Plants (ICAPP '10), June, 2010, San Diego, CA, US.
14)J. Xiong, S. Koshizuka, M. Sakai, H. Okada, M. Naitoh, S. Uchida, Evaluation of Mechanical Load on Wet Wall Impacted by High-speed Droplet Using MPS Method, 2010 Spring Meeting of Atomic Energy Society of Japan, March, 2010, Mito, Japan
15)J. Xiong, S. Koshizuka, M. Sakai, Investigation on Mitigation Effects by Water Film During Liquid Droplet Impingement, 3rd Joint International Symposium on Nuclear Science and Technology "Global Sustainability and Nuclear Engineering, Education and Research", January, 2010, Shanghai, China. (Poster presentation)
16)J. Xiong, S. Koshizuka, M. Sakai, Numerical Analysis of Liquid Droplet Impingement onto a Wet Wall Using MPS Method, 2nd Anniversary Symposium of GoNERI, 2009, Tokyo, Japan
17)J. Xiong, S. Koshizuka, M. Sakai, Numerical Analysis of Droplet Impingement with a Thin Water Film on the Wall Using MPS Method, The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), Paper No. N13P1115, Sept., 2009, Kanazawa, Japan.
18)J. Xiong, S. Koshizuka, M. Sakai, Evaluation of Mechanical Load on the Piping Wall Induced by Droplet Impingement Using MPS Method, 2009 Fall Meeting of Atomic Energy Society of Japan, Sept., 2009, Sendai, Japan
19)J. Xiong, S. Koshizuka, M. Sakai, Numerical Analysis of Droplet Impingement Using the Moving Particle Semi-implicit Method, The International Summer School of Nuclear Power Plants & Young Generation Workshop, August 2009, Ibaraki, Japan. (Poster presentation).
20)J. Xiong, J. Arai, S. Koshizuka, Numerical Analysis of Droplet Impingement on a wetted wall Using MPS method, 2nd Joint International Symposium on Nuclear Science and Technology "Global Sustainability and Nuclear Engineering, Education and Research", March 2009, Ibaraki, Japan. (Poster presentation)
21)J. Xiong, Y., Yang, X. Cheng, Effects of Spray Modes on Hydrogen Risk in a Chinese NPP, OECD/NEA Workshop on Experiments and CFD Code Applications to Nuclear Reactor Safety (XCFD4NRS), Sep., 2008, Grenoble, France,CO-7.
22)J. Xiong, Y., Yang, X. Cheng, Effects of Spray Activation on Hydrogen Risk Using GASFLOW, International workshop on Passive Safety Systems in Advanced PWRs (IPASS’08), April, 2008, Shanghai, China, H-04.
23)J. Xiong, Y., Yang, X. Cheng, CFD Analysis on Hydrogen Safety in A Chinese NPP, SJTU-UT Joint Workshop on Nuclear Engineering 2008, Shanghai, China, March, 2008
24)J. Xiong, Y., Yang, X. Cheng, CFD Studies on Hydrogen and Steam Behavior in the NPP Containment during Severe Accidents, Joint International Symposium on Nuclear Science and Technology -- “Global Sustainability and Nuclear Engineering, Education and Research”, Xi’an, China, March, 2008
25)J. Xiong, Y., Yang, X. Cheng, Studies on Hydrogen Behavior in the Qinshan-II NPP containment, Proceeding of ICONE-15. 15th International Conference on Nuclear Engineering, April, 2007, Nagoya, Japan, ICONE-10384.

教学工作 核反应堆物理 ， 本科三年级 ， 51学时 ， 3 学分
反应堆数值计算及其应用，本科四年级，32 学时，2学分
核工程课程设计， 本科四年级 ， 51学时， 3 学分
高等反应堆工程，研究生，54学时，3学分

学术兼职 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) Track Leader, Technical Program Committee Member
11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Technical Program Assistant Chair
8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8)分会场主席；
6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6),分会场主席 ；
International Seminar on Subchannel Analysis CFD modeling and verification, CHF experiment and benchmarking,分会场主席；
AC21 International CFD Workshop for Young Nuclear Engineers 技术委员会主席；
The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10)分会场主席；
Frontier in Energy Research的Review Editor；

荣誉奖励 2017年，上海交通大学首届“教书育人奖”提名奖；
2016年，上海交通大学“十佳班主任”；
2015年，上海交通大学“SMC-晨星****奖励计划”优秀青年教师(B)类；
2013年，上海市浦江人才计划(A)类。