熊进标
发布时间：2018-11-29 10:03:03
 |
熊进标 副教授
所在系所核科学与工程学院
办公电话021-34204917 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
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
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
反应堆热工水力；
核电站安全、严重事故；
CFD在核反应系统中的应用及验证；
湍流的激光测量及湍流模拟；
两相流试验研究及先进模拟方法
核电站安全、严重事故；
CFD在核反应系统中的应用及验证；
湍流的激光测量及湍流模拟；
两相流试验研究及先进模拟方法
科研项目
2017-2020，国家自然科学基金项目：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；
2016-2018，大型先进压水堆核电站重大专项核电关键软件评估课题，第四子课题负责人；
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；
2011-2015，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，核能开发科研项目：堆内超临界辐照实验回路设计技术研究，主要技术骨干；
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；
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；
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；
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；
2014-2015，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
2016-2018，大型先进压水堆核电站重大专项核电关键软件评估课题，第四子课题负责人；
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；
2011-2015，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，核能开发科研项目：堆内超临界辐照实验回路设计技术研究，主要技术骨干；
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；
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；
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；
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；
2014-2015，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
代表性论文专著
SCI期刊文章
1)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).
2)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).
3)J. Xiong, X. Cheng. Turbulence modelling for supercritical pressure heat transfer in upward tube flow. Nuclear Engineering and Design 270, 249-258 (2014).
4)J. Xiong, et al.. Laser Doppler measurement and CFD validation in 3x3 bundle flow. Nuclear Engineering and Design 270, 396-403 (2014).
5)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).
6)H. Wang, J. Xiong, X. Cheng. Evaluation of Turbulence Model Performance in Predicting 3x3 Bundle Flows,Nuclear Power Engineering,35(4),2014.(in Chinese)
7)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).
8)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).
9)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)
10)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)
11)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.
12)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.
13)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.
EI期刊文章
[1] 王红燕，熊进标，程旭。3×3棒束湍流流动的数值模拟研究。核动力工程，35卷4期（2014）。
[2] 熊进标，杨燕华。秦山二期核电站氢气风险的CFD研究。核动力工程，35(4), 8-13 （2009）。
国际会议文章
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.
国内会议文章
[1] 熊进标，程旭。基于MPS方法的复杂表面液滴冲击数值模拟。2012核系统设计重点实验室年会。成都。2012年11月22-23日。
[2] 俞洋，熊进标，程旭. 3D多普勒测量技术应用于3x3棒束间湍流流动测量[C]. 第十三届反应堆热工流体学术年会，上海，中国，2013.
1)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).
2)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).
3)J. Xiong, X. Cheng. Turbulence modelling for supercritical pressure heat transfer in upward tube flow. Nuclear Engineering and Design 270, 249-258 (2014).
4)J. Xiong, et al.. Laser Doppler measurement and CFD validation in 3x3 bundle flow. Nuclear Engineering and Design 270, 396-403 (2014).
5)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).
6)H. Wang, J. Xiong, X. Cheng. Evaluation of Turbulence Model Performance in Predicting 3x3 Bundle Flows,Nuclear Power Engineering,35(4),2014.(in Chinese)
7)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).
8)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).
9)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)
10)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)
11)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.
12)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.
13)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.
EI期刊文章
[1] 王红燕，熊进标，程旭。3×3棒束湍流流动的数值模拟研究。核动力工程，35卷4期（2014）。
[2] 熊进标，杨燕华。秦山二期核电站氢气风险的CFD研究。核动力工程，35(4), 8-13 （2009）。
国际会议文章
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.
国内会议文章
[1] 熊进标，程旭。基于MPS方法的复杂表面液滴冲击数值模拟。2012核系统设计重点实验室年会。成都。2012年11月22-23日。
[2] 俞洋，熊进标，程旭. 3D多普勒测量技术应用于3x3棒束间湍流流动测量[C]. 第十三届反应堆热工流体学术年会，上海，中国，2013.
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
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；
2016年，上海交通大学“十佳班主任”；
2015年，上海交通大学“SMC-晨星学者奖励计划”优秀青年教师(B)类；
2013年，上海市浦江人才计划(A)类。
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-晨星学者奖励计划”优秀青年教师(B)类；
2013年，上海市浦江人才计划(A)类。
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