近期论文
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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.
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