2008-2011，東京大學(xué) 系統(tǒng)創(chuàng)新專業(yè)，博士
2005-2008，上海交通大學(xué) 核能科學(xué)與工程專業(yè)，碩士
2001-2005，西安交通大學(xué) 核工程與核技術(shù)專業(yè)，學(xué)士

2023年至今    上海交通大學(xué)  機(jī)械與動(dòng)力工程學(xué)院    教授、   博士生導(dǎo)師

2015年-2022年    上海交通大學(xué)  機(jī)械與動(dòng)力工程學(xué)院    副教授、博士生導(dǎo)師
2011年-2014年    上海交通大學(xué)  機(jī)械與動(dòng)力工程學(xué)院    講師

核反應(yīng)堆熱工水力與安全；

核反應(yīng)堆高保真熱工水力分析；
反應(yīng)堆流場(chǎng)高時(shí)空分辨光學(xué)測(cè)量；
兩相流動(dòng)沸騰的多物理場(chǎng)可視化測(cè)量；
先進(jìn)核能系統(tǒng)多物理耦合分析；
反應(yīng)堆堆芯數(shù)字孿生與人工智能應(yīng)用。

中國核學(xué)會(huì)核反應(yīng)堆熱工流體力學(xué)分會(huì)副秘書長(zhǎng)；

中國核學(xué)會(huì)核能動(dòng)力分會(huì)常務(wù)理事；
中子科學(xué)與技術(shù)全國重點(diǎn)實(shí)驗(yàn)室學(xué)術(shù)委員會(huì) 委員；
Nuclear Eningeering and Design(SCI)  期刊編委；
Annals of Nuclear Energy(SCI)   期刊編委；
Nuclear Engineering and Technology(SCI)   期刊編委；
《核動(dòng)力工程》編委；
《原子能科學(xué)技術(shù)》青年編委。

2024-2027，國家自然科學(xué)基金企業(yè)創(chuàng)新聯(lián)合基金重點(diǎn)項(xiàng)目：螺旋多葉型核燃料多相共軛傳熱的高分辨試驗(yàn)測(cè)量與高保真數(shù)值模擬研究，主持；
2022-2025，國家重點(diǎn)研發(fā)計(jì)劃青年科學(xué)家項(xiàng)目：核反應(yīng)堆全堆芯三維高精度高分辨率核熱耦合鏡像技術(shù)研究，主持；
2021-2024，國家自然科學(xué)基金面上項(xiàng)目：基于多物理場(chǎng)同步可視化的窄通道壁面沸騰機(jī)理模型構(gòu)建，主持；
2018-2020，國家重點(diǎn)實(shí)驗(yàn)室基金：熔池行為數(shù)值模擬的MPS基礎(chǔ)模型研究，主持；
2017-2020，國家自然科學(xué)基金面上項(xiàng)目：耐事故核燃料碳化硅包殼表面腐蝕形貌對(duì)沸騰傳熱性能影響的機(jī)理研究，主持；
2017-2020,  科技部大型先進(jìn)壓水堆核電站重大專項(xiàng)課題：全子通道截面單相可視化及過渡沸騰實(shí)驗(yàn)研究，主持；
2017-2020，核能開發(fā)項(xiàng)目子課題：燃料組件堆外轉(zhuǎn)運(yùn)中換熱特性試驗(yàn)研究，主持；
2016-2019，科技部大型先進(jìn)壓水堆核電站重大專項(xiàng)課題：嚴(yán)重事故熔融物與水相互作用3D分析程序的確認(rèn)和模型評(píng)估，主持；
2016-2017，國家重點(diǎn)實(shí)驗(yàn)室基金：基于PIV方法的棒束通道流場(chǎng)測(cè)量研究，主持；
2014-2015，國家重點(diǎn)實(shí)驗(yàn)室基金：棒束流動(dòng)的激光多普勒測(cè)速及湍流模擬研究，主持；
2014-2015，教育部留學(xué)回國人員基金：T形管內(nèi)熱攪混的實(shí)驗(yàn)與數(shù)值研究，主持；
2013-2015，上海市浦江人才計(jì)劃項(xiàng)目：基于折射率補(bǔ)償激光測(cè)量的棒束流動(dòng)研究，主持；
2013-2014，國際原子能機(jī)構(gòu)協(xié)調(diào)研究計(jì)劃課題：Verification and Validation of CFD Code in Single-Phase Bundle Flows，主持；
2012-2015，國家自然科學(xué)基金項(xiàng)目：基于超臨界流體傳熱弱化機(jī)理的湍流模型開發(fā)，主持；
2012-2012，日本東京大學(xué)合作研究課題： Study of Secondary Flow Effect for Flow-Accelerated Corrosion in Nuclear Power Plants, 主持；
2011-2015，科技部大型先進(jìn)壓水堆核電站重大專項(xiàng)：核電軟件課題之棒束內(nèi)流動(dòng)傳熱行為試驗(yàn)與驗(yàn)證研究，主持；
2011-2015，大型先進(jìn)壓水堆核電站重大專項(xiàng)三維熔融物-水相互作用分析程序開發(fā)子課題, 技術(shù)負(fù)責(zé)人；
2011-2014，核能開發(fā)項(xiàng)目：堆內(nèi)超臨界輻照實(shí)驗(yàn)回路設(shè)計(jì)技術(shù)研究，主要技術(shù)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.


會(huì)議文章
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.