2008-2011，东京大学 系统创新专业，博士
2005-2008，BETVLCTOR伟德在线登录平台 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

2023年1月 至今 BETVLCTOR伟德在线登录平台 BETVLCTOR伟德在线登录平台 核科学与工程学院 教授、 博士生导师
2015年-2022年 BETVLCTOR伟德在线登录平台 BETVLCTOR伟德在线登录平台 核科学与工程学院 副教授、博士生导师
2011年-2014年 BETVLCTOR伟德在线登录平台 BETVLCTOR伟德在线登录平台 核科学与工程学院 讲师

先进核能系统热工水力；
反应堆流场高分辨测量技术；
两相流动沸腾的可视化测量技术；
反应堆流动传热精细化模拟；
核反应堆多物理耦合分析；
反应堆堆芯数字孪生技术。

2022-2025，国家重点研发计划青年科学家项目：核反应堆全堆芯三维高精度高分辨率核热耦合镜像技术研究，主持；
2021-2024，国家自然科学基金面上项目：基于多物理场同步可视化的窄通道壁面沸腾机理模型构建，主持；
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，主持；
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，主持；
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，主持；
2017-2020，核能开发项目子课题：燃料组件堆外转运中换热特性试验研究，主持；
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，主持；
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，主持；
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，主持；
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，主持；
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，主持；
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，主持；
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，主持；
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, 主持；
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，主持；
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；

SCI期刊文章
1. Yang Y, Xiong J. Unified two-component interfacial area concentration model for narrow channel two-phase flow. International Journal of Multiphase Flow. 2023;163:104428.
2. Xiong J, Xie H, Du S, Cheng X. Experimental measurement of bubbly two-phase flow in a 4x4 rod bundle with wire mesh sensor. Applied Thermal Engineering. 2023;218:119294.
3. Wang J, Wang H, Xiong J. Experimental investigation on microlayer behavior and bubble growth based on laser interferometric method. 2023;11.
4. Wang H, Xiong J, Wang J. Development and assessment of five-component wall boiling heat flux partitioning model. International Journal of Multiphase Flow. 2023;158:104306.
5. Wang H, Lu C, Qu W, Xiong J. Experimental investigation on flow field around a flapping plate with single degree of freedom. Nuclear Engineering and Technology. 2023;55(6):1999-2010.
6. Qu W, Xie H, Shen D, Wang Z, Xiong J. Experimental study of coherent structures downstream mixing vaned spacer grid of different inclination angles in a 5 × 5 rod bundle by TR-PIV. Annals of Nuclear Energy. 2023;181:109516.
7. Qu W, Liu L, Yao W, Xie H, Liu J, Xiong J. Time-resolved PIV measurement of coherent structures downstream of step blockage in a narrow rectangular channel. Annals of Nuclear Energy. 2023;180:109505.
8. Li T, Xiong J, Zhang T, Chai X, Liu X. Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system. Annals of Nuclear Energy. 2023;187:109774.
9. Yang Y, Xiong J. Development of a novel flexible printed circuit sensor and post-processing algorithm for two-phase flow measurement in narrow rectangular channels. Experimental Thermal and Fluid Science. 2022;136:110650.
10. Li T, Du Z, He H, He X, Qu W, Xiong J. Experimental investigation on effective thermal conductivity of powder-packed assembly gaps in heat pipe cooled reactor core. Nuclear Engineering and Design. 2022;388:111611.
11. Hassan M, Xiong J, Cheng X, Liu D. Uncertainty quantification (UQ) for CFD simulation of OECD-NEA cold leg mixing benchmark. Nuclear Engineering and Design. 2022;393:111799.
12. Hassan M, Xiong J, Cheng X. Large-eddy simulation of the OECD-NEA cold-leg mixing benchmark. Annals of Nuclear Energy. 2022;167:108826.
13. Zhu Y, Xiong J, Yang Y. MPS eutectic reaction model development for severe accident phenomenon simulation. Nuclear Engineering and Technology. 2021;53(3):833-41.
14. Wiltschko F, Qu W, Xiong J. Validation of RANS models and Large Eddy simulation for predicting crossflow induced by mixing vanes in rod bundle. Nuclear Engineering and Technology. 2021;53(11):3625-34.
15. Wang Z, Zhong M, Deng J, Liu Y, Huang H, Zhang Y, et al. Experimental investigation on the transient film boiling heat transfer during quenching of FeCrAl. Annals of Nuclear Energy. 2021;150.
16. Qu W, Yao W, Xiong J, Cheng X. Experimental Study of Pressure Loss in a 5 × 5–Rod Bundle With the Mixing Vane Spacer Grid. Frontiers in Energy Research. 2021;9:675494.
17. Hassan M, Xiong J, Cheng X. Unsteady RANS simulation of OECD-TAMU cold-leg mixing benchmark. Nuclear Engineering and Design. 2021;372:110978.
18. Zhu Y, Qiu Z, Xiong J, Yang Y. Verification and validation of MPS potential force interface tension model for stratification simulation. Annals of Nuclear Energy. 2020;148:13.
19. Xiong JB, Qu WH, Zhang TF, Chai X, Liu XJ, Yang YH. Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly. Annals of Nuclear Energy. 2020;143.
20. Xiong JB, Lu C, Qu WH, Yang YH, Cheng X. Assessment of RANS models in predicting mixing flow induced by split -type vanes in rod bundle. Nuclear Engineering and Design. 2020;363.
21. Xiong JB, Lu C, Qu WH. Validation for CFD Simulation in Rod Bundles With Split-Vane Spacer Grids Based on LDA Measurement. Frontiers in Energy Research. 2020;8.
22. Xiong J, Wu Z, Chen X, Zhang T. Experimental and analytical study on heat dissipation mechanisms during spent fuel unloading in sodium fast reactor. Annals of Nuclear Energy. 2020;136.
23. Xiong J, Wang Z, Xiong P, Lu T, Yang Y. Experimental investigation on transient boiling heat transfer during quenching of fuel cladding surfaces. International Journal of Heat and Mass Transfer. 2020;148.
24. Wang Z, Qu W, Xiong J, Zhong M, Yang Y. Investigation on effect of surface properties on droplet impact cooling of cladding surfaces. Nuclear Engineering and Technology. 2020;52(3):508-19.
25. Xiong J, Zhu Y, Zhang T, Cheng X. Lagrangian simulation of three-dimensional macro-scale melting based on enthalpy method. Computers & Fluids. 2019;190:168-77.
26. Wang Z, Xiong J, Yao W, Qu W, Yang Y. Experimental investigation on the Leidenfrost phenomenon of droplet impact on heated silicon carbide surfaces. International Journal of Heat and Mass Transfer. 2019;128:1206-17.
27. Qu W, Xiong J, Chen S, Qiu Z, Deng J, Cheng X. PIV measurement of turbulent flow downstream of mixing vane spacer grid in 5x5 rod bundle. Annals of Nuclear Energy. 2019;132:277-87.
28. Qu W, Xiong J, Chen S, Cheng X. High-fidelity PIV measurement of cross flow in 5 x 5 rod bundle with mixing vane grids. Nuclear Engineering and Design. 2019;344:131-43.
29. Qu W, Wang Z, Xiong J, Cheng X. Experimental study of cross flow and lateral pressure drop in a 5 x 5 rod bundle with mixing vane spacer grid. Nuclear Engineering and Design. 2019;353.
30. Jin D, Xiong J, Cheng X. Investigation on interphase force modeling for vertical and inclined upward adiabatic bubbly flow. Nuclear Engineering and Design. 2019;350:43-57.
31. Xiong J, Qu W, Wu Z, Cheng X. PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction. Annals of Nuclear Energy. 2018;120:540-5.
32. Xiong J, Cheng R, Lu C, Chai X, Li X, Cheng X. CFD simulation of swirling flow induced by twist vanes in a rod bundle. Nuclear Engineering and Design. 2018;338:52-62.
33. Xiong J, Cheng X, Yang Y. Numerical analysis on supercritical water heat transfer in a 2 x 2 rod bundle. Annals of Nuclear Energy. 2015;80:123-34.
34. Xiong J, Yu Y, Yu N, Fu X, Wang H, Cheng X, et al. Laser Doppler measurement and CFD validation in 3 x 3 bundle flow. Nuclear Engineering and Design. 2014;270:396-403.
35. Xiong J, Yu N, Yu Y, Fu X, Cheng X, Yang Y. Experimental investigation on anisotropic turbulent flow in a 6 x 6 rod bundle with LDV. Nuclear Engineering and Design. 2014;278:333-43.
36. Xiong J, Cheng X, Yang Y. Numerical investigation on mass transfer enhancement downstream of an orifice. International Journal of Heat and Mass Transfer. 2014;68:366-74.
37. Xiong J, Cheng X. Turbulence modelling for supercritical pressure heat transfer in upward tube flow. Nuclear Engineering and Design. 2014;270:249-58.
38. Xiong J, Koshizuka S, Sakai M, Ohshima H. Investigation on droplet impingement erosion during steam generator tube failure accident. Nuclear Engineering and Design. 2012;249:132-9.
39. Sakai M, Shigeto Y, Sun X, Aoki T, Saito T, Xiong J, et al. Lagrangian-Lagrangian modeling for a solid-liquid flow in a cylindrical tank. Chemical Engineering Journal. 2012;200:663-72.
40. Xiong J, Koshizuka S, Sakai M. Investigation of Droplet Impingement onto Wet Walls Based on Simulation Using Particle Method. Journal of Nuclear Science and Technology. 2011;48(1):145-53.
41. Xiong J, Koshizuka S, Sakai M. Turbulence modeling for mass transfer enhancement by separation and reattachment with two-equation eddy-viscosity models. Nuclear Engineering and Design. 2011;241(8):3190-200.
42. Okada H, Uchida S, Naitoh M, Xiong J, Koshizuka S. Evaluation Methods 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. 2011;48(1):65-75.
43. Xiong J, Koshizuka S, Sakai M. Numerical Analysis of Droplet Impingement Using the Moving Particle Semi-implicit Method. Journal of Nuclear Science and Technology. 2010;47(3):314-21.
44. Xiong J, Yang Y, Cheng X. CFD Application to Hydrogen Risk Analysis and PAR Qualification. Science and Technology of Nuclear Installations. 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.

核反应堆安全分析，本科三年级 ， 32学时 ， 2 学分
反应堆数值计算及其应用，本科四年级，32 学时，2学分
高等反应堆工程，研究生，51学时，3学分
核反应堆设计原理（全英文授课），研究生，51学时，3学分

Nuclear Eningeering and Design (SCI) 期刊编委；
Annals of Nuclear Energy (SCI) 期刊编委；
《核动力工程》（EI）期刊编委；
Frontier in Nuclear Engineering期刊副编辑；
Frontier in Energy Research的Review Editor.

2021年，中国核学会青年奖；
2017年，BETVLCTOR伟德在线登录平台首届“教书育人奖”提名奖；
2016年，BETVLCTOR伟德在线登录平台“十佳班主任”；
2015年，BETVLCTOR伟德在线登录平台“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。