Veröffentlichungen seit 2013

Zeitschriften

 

  • Hong Xu, Aurelian Florin Badea, Xu Cheng. Studies on the criterion for choking process in two-phase flow. Progress in Nuclear Energy 133 (2021) 103640

  • Hong Xu, Aurelian Florin Badea, Xu Cheng. Analysis of two phase critical flow with a non-equilibrium model. Nuclear Engineering and Design 372 (2021) 110998

  • Meng Zhao, FangnianWang, Aurelian Florin Badea. Evaluation and development of heat transfer model for supercritical water flowing in 2 × 2 rod bundles with spacer grid. Volume 165, Part B, February 2021, 120702

  • Kryková, M., Schulenberg, T., Arnoult Růžičková, M., Sáez-Maderuelo, A., Otic, I., Czifrus, S., Cizelj, L., Pavel, G. L. "European Research Program on Supercritical Water-Cooled Reactor." ASME J of Nuclear Rad Sci. April 2021; 7(2): 021301, https://doi.org/10.1115/1.4048901

  • Xu, H., Badea, Aurelian F., Cheng, X., 2020. Sensitivity analysis of thermal-hydraulic models based on FFTBM-MSM two-layer method for PKL IBLOCA experiment, Annals of Nuclear Energy 147 (2020) 107732

  • Jure Oder, Iztok Tiselj, Wadim Jäger, Thomas Schaub, Wolfgang Hering, Ivan Otic, Afaque Shams, "Thermal fluctuations in low-Prandtl number fluid flows over a backward facing step", Nuclear Engineering and Design, Volume 359, 2020, ISSN 0029-549

  • Liu, X.J., Yang, T., Chai, X., Xiong, J.B., Zhang, T.F., Cheng, X., 2020. Preliminary safety analysis for the SCWR-FQT facility, Int. J Energy Res. 2020; 44: 8103–8112.

  • Cheng, X., Wielenberg, A., Hampel, U., Starflinger, J., Gupta, S., Schaffrath, A. and Weyermann, F., 2020. Summary of 3rd Sino-German symposium on fundamentals of advanced nuclear safety technology, Kerntechnik, 85 (2020) 2

  • Wang, F.N, Cheng, X., 2020. Extension and validation of aerosol wash-down model on inclined wall, Annals of Nuclear Energy 144 (2020) 107506

  • Xiong, J.B., Lu C., Qu W.H., Yang, Y.H., Cheng, X., 2020. Assessment of RANS models in predicting mixing flow induced by split-type vanes in rod bundle, Nuclear Engineering and Design 363 (2020) 110615

  • Liu, X.J., Yang, D.M., Yang, Y., Chai, X., Xiong, J.B., Zhang, T.F., Cheng, X., 2020. Computational fluid dynamics and subchannel analysis of lead–bismuth eutectic-cooled fuel assembly under various blockage conditions. Applied Thermal Engineering. 2020 Jan 5; 164:114419.

  • Liu, X.J., Wang, Q., He, Z., Chen, K., Cheng, X., 2019. Phenomena identification and ranking table exercise for thorium based molten salt reactor-solid fuel design. Frontiers in Energy.:1-8.

  • Zhang, T., Xiong, J.B., Liu, X.J., Chai, X., Li, W., Cheng, X., 2019. Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant. International Journal of Energy Research, 2019 Nov; 43(14):8286-98.

  • Liu, X.J., Song, M.Q., Cheng, X., 2019. Current status and challenges of supercritical fluid thermal hydraulics. Nuclear Engineering and Design. 2019 Dec 1;354:110176.

  • Qu, W., Xiong, J.B., Chen, S., Cheng,  X., 2019. High-fidelity PIV measurement of cross flow in 5× 5 rod bundle with mixing vane grids. Nuclear Engineering and Design. 2019 Apr 1; 344,:131-43.

  • Qu, W., Wang, Z., Xiong, J.B., Cheng, X., 2019. Experimental study of cross flow and lateral pressure drop in a 5× 5 rod bundle with mixing vane spacer grid. Nuclear Engineering and Design. 2019 Nov 1;353:110209.

  • Xu, W., Guo, J., Liu, X.J., Xiong, J.B., Chai, X., Zhang, T., Cheng, X., Zeng, W., 2019. Predictions of quench temperature and quench velocity in narrow rectangular channel of novel plate-type reactor, Annals of Nuclear Energy. 2019 Sep 1;131:148-55.

  • Jin, D., Xiong, J.B., Cheng, X., 2019. Investigation on interphase force modeling for vertical and inclined upward adiabatic bubbly flow. Nuclear Engineering and Design. 2019 Aug 15; 350:43-57.

  • Wang, F.N., Cheng, X., 2019. Modeling approach of flowing condensate coverage rate on inclined wall for aerosol wash down, Nuclear Engineering and Design 355 (2019) 110349

  • Shen, D.H., Liu, X.J., Cheng, X., 2019. A study on geometric shape factors for turbulent mixing coefficients in rod bundles, Nuclear Engineering and Design (2019) 353

  • Luo Y, Liu X, Cheng X. IVR-ERVC study of 1700 MW class PWR based on MAAP simulation and coupled analysis, Annals of Nuclear Energy, 2019, 126: 1-9.

  • Cheng, X., Zhao, M., Feuerstein, F., Liu, X.J., 2019. Prediction of heat transfer to supercritical water at different boundary, International Journal of Heat and Mass Transfer 133 (2019) 527-536

  • Jure Oder, Iztok Tiselj, Wadim Jäger, Thomas Schaub, Wolfgang Hering, Ivan Otic, Afaque Shams. Thermal Fluctuations in Low-Prandtl Number Fluid Flows over a Backward Facing Step, Nuclear Engineering and Design, submitted 2019.

  • Yang, Z, Cheng, X., Zheng, X.H., Chen, H-S., 2019. Numerical investigation on heat transfer of the supercritical fluid upward in vertical tube with constant wall temperature, International Journal of Heat and Mass Transfer 128 (2019) 875–884

  • Wang, X., Cheng, X., 2018. Analysis of inter-channel sweeping flow in wire wrapped 19-rod bundle, Nuclear Engineering and Design 333 (2018) 115–121

  • Shen, D.H., Liu, X.J., Cheng, X., 2018. A new turbulent mixing modeling approach for sub-channel analysis code, Annals of Nuclear Energy 121 (2018) 194–202

  • Cheng, X., Feuerstein, F., Klingel, D., Yu, D.L., Mechanistic prediction of post dryout heat transfer and rewetting, Kerntechnik 83 (2018) 3, Carl Hanser Verlag, München

  • Xiong, J.B., Qu, W.H., Wu, Z.H., Cheng, X., 2018. PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction, Annals of Nuclear Energy 120 (2018) 540–545

  • Liu, X.J., Luo, Y.J., Cao, Z., Guo, R., Cheng, X., 2018. Safety research of IVR-ERVC for advanced water cooled reactor, Energy 156 (2018) 458-467

  • Badea, Aurelian F., Zhao, M., Cheng, X., Feuerstein, F., Liu, X.J., 2018. Consistency considerations on a large databank and wide range heat transfer prediction for supercritical water in circular tubes, Nuclear Engineering and Design 335 (2018) 178–185

  • M. Zhao, X. Liu, A.F. Badea, F. Feuerstein and X. Cheng. Comparison of heat transfer models with databank of supercritical fluid, Kerntechnik, Volume 83, Issue 3 (2018) 237-239

  • Yu, D.L., Feuerstein, F., Koeckert, L., Cheng, X., 2018. Analysis and modeling of post-dryout heat transfer in upward vertical flow, Annals of Nuclear Energy 115 (2018) 186–194

  • Yang, T., Liu, X.J., Cheng, X., 2018. A circumferentially non-uniform fuel model and its application to thermal-hydraulic code, International Journal of Energy Research, 42(1): 188~197, 2018

  • Cheng, X., Liu, X.J., 2017. Research Challenges of Heat Transfer to Supercritical Fluids, J of Nuclear Eng. and Rad Sci 4(1), 011003

  • Dan G. Cacuci, Aurelian F. Badea, Madalina C. Badea, James J. Peltz. Efficient computation of operator-type response sensitivities for uncertainty quantification and predictive modeling: illustrative application to a spent nuclear fuel dissolver model” International Journal for Numerical Methods in Fluids 83 (2017) 149-174.

  • Aurelian F. Badea, Dan G. Cacuci. Predictive uncertainty reduction in coupled neutron-kinetics/thermal hydraulics modeling of the BWR-TT2 benchmark, Nuclear Engineering and Design 313 (2017) 330–344.

  • Pang, B., Cheng, X., 2017. Assessment of two-phase interchannel mixing models for BWR and PWR conditions, Annals of Nuclear Energy 01/2017; 99: 283-291

  • Feuerstein, F., Coelho Silva, A., Klingel, D., Cheng, X., 2017. Large/scale heat transfer experiments with supercritical R134a flowing upward in a circular tube, atw vol.62 (2017), issue 2, pp.121 – 125, February 2017

  • Cheng, X., Yang, Y.H., Liu, X.J., 2016. Super-Critical Water Reactor with Mixed Spectrum: Design and Key Technologies, Shanghai Jiao Tong University Press, 2016, ISBN 978-7-313-14195-8

  • Cheng, X., Yang, Y.H., 2016. Status and Challenges of Nuclear Thermal-Hydraulics Research in China for Water-Cooled Reactors, Nuclear Technology, Vol.196, No.2, November 2016, pp.175 – 186

  • Huang, X., Cheng, X., Klein-Hessling, W., 2016. Evaluation of Passive Containment Cooling with an Advanced Water Film Model in a Lumped-Parameter Code, Nuclear Technology, Vol.196, No.2, November 2016, pp.248 – 259

  • Xue Zhou Jin, Bradut-Eugen Ghidersa, Aurelian Florin Badea. HELOKA-HP thermal-hydraulic model validation and calibration, Fusion Engineering and Design 109-111, Part B (2016), 1242-1246.

  • James J. Peltz, Dan Gabriel Cacuci, Aurelian Florin Badea, Madalina C. Badea. Predictive Modeling Applied to a Spent Fuel Dissolver Model—II: Uncertainty Quantification and Reduction, Nuclear Science and Engineering 183 (2016) 332-346.

  • Cheng, X., 2016. Numerical simulation of multi-phase phenomena in IVR related processes, Kerntechnik 81 (2016) 2, pp.160-163

  • Liu, X.J., Cheng, X., 2016. Validation of the ATHLET-SC code by trans-critical data, Kerntechnik 81 (2016) 2, pp.164-166

  • Zhao, M., Gu, H.Y., Li, H.B., Cheng, X., 2016. Heat transfer of water flowing upward in vertical annuli with spacers at high pressure conditionsof Annals, Nuclear Energy, volume 87, 2016, pp. 209 – 216

  • Cheng, X., et al. 2015. European Activities on Crosscutting Thermal-hydraulic phenomena for innovative nuclear systems, Nuclear Engineering and Design, 290 (2015), 2-12.

  • Zimmermann, M., Cheng, X., Otic, Sieber, G., Goodheart, K., 2015. Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers, Annals of Nuclear Energy, 85(2015), 403-417.

  • Agbodemegbe, V.Y., Cheng, X., Akaho, E.H.K., Allotey, F.K.A., 2015. Correlation for cross-flow resistance coefficient using STAR-CCM+simulation data for flow of water through rod bundle supported byspacer grid with split-type mixing vane, Karlsruhe, Nuclear Engineering and Design 285 (2015) 134-149.

  • Xiong, J.B., Yang, Y.H., Cheng, X., 2015. Numerical analysis on supercritical water heat transfer in a 2x2 rod bundle, Annals of Nuclear Energy, 85(2015),123-134.

  • Cao, Z, Liu, X.J., Cheng, X.,2015. A two dimensional approach for temperature distribution in reactor lower head during severe accident, Annals of Nuclear Energy,85 (2015), 467-480.

  • Jin, Y., Xu, W., Liu, X.,J., et al., 2015. In-and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR. Annals of Nuclear Energy, 2015, 80: 322-337.

  • Dan Gabriel Cacuci, Aurelian Florin Badea, Predictive modeling methodology for obtaining optimally predicted results with reduced uncertainties: Illustrative application to a simulated solar collector facility, Solar Energy 119 (2015) 486-506.

  • Yu, Y.Q., Cheng, X, 2014. Experimental study of water film flow on large vertical and inclined flat plate, Progress in Nuclear Energy, volume 77(2014), 176-186.

  • Chai, X., Otic, I., Cheng, X., 2014. A new drag force model for the wake acceleration effect and its application to simulation of bubbly flow, Progress in Nuclear Energy 80 (2015), 24-36.

  • Chai, X., Cheng, X., 2014. Wake acceleration effect on spherical bubbles aligned in-line, Progress in Nuclear Energy 80 (2015), 74-79.

  • Huang, X., Cheng, X., 2014. Modification and application of water film model in COCOSYS for PWR’s passive containment cooling, Nuclear Engineering and Design 280 (2014), 251-261.

  • Peng, B., Cheng, X., 2014. Proposal of a new type of two-phase interchannel mixing model for application to subchannel analysis of PWR conditions, Annals of Nuclear Energy 73 (2014) 108-121

  • Yu, Y.Q., Cheng, X, 2014. Experimental study of water film flow on large vertical and inclined flat plate, Progress in Nuclear Energy, volume 77(2014), 176-186.

  • D.G. Cacuci, A.F. Badea, M.C. Badea. Thermal solar collector predictive modeling: I. Adjoint sensitivity analysis. Transactions of the American Nuclear Society 111 (2014), 1474-1477.

  • Guo, R., Kuang, B., Cheng, X., A theoretical CHF model for subcooled flow boiling in a curved channel at low pressure. Annals of Nuclear Energy, 2014, 69:196-202.

  • Xiong, J.B., Cheng, X., Turbulence modelling for supercritical pressure heat transfer in upward tube flow, Nuclear Engineering and Design, 2014, 270, 249-258.

  • Zhao, M., Gu, H.Y., Cheng, X., Experimental study on heat transfer of supercritical water flowing downward in circular tubes. Annals of Nuclear Energy, 2014, 63: 339-349.

  • Liu, X.J., Yang, T., Cheng, X., 2013. Thermal-hydraulic analysis of flow blockage in a supercritical water-cooled fuel bundle with sub-channel code, Annals of Nuclear Energy, Annals of Nuclear Energy 59 (2013) 194–203

  • Zhou, C., Huber, K., Cheng, X., 2013. Validation of the modified ATHLET code with the natural convection test of the PHENIX reactor, Annals of Nuclear Energy, 2013, 59: 31-46

  • Cheng, X., 2013. R&D on Nuclear Safety and Severe Accident Mitigation in China, Asia Research Policy, Volume 4, Issue 1, 2013

 

Konferenzen

 

  • Xu Cheng, Aurelian F. Badea, Meng Zhao. Application of the ATHLET Code to Supercritical Water Cooled Systems, 50th Annual Meeting on Nuclear Technology (AMNT 2019) Berlin, 7 – 8 May 2019

  • F. Wang et al. Modeling approach of flowing condensate coverage on inclined wall for aerosol wash down, AMNT 2019, 7-8 May, Berlin, Germany.

  • L. Köckert, F. Feuerstein, D. Yu, D. Klingel, X. Cheng, “Comparison of Post-Dryout Heat Transfer Measurements in an R-134a Cooled Tube and Selected Correlations”, 50th Annual Meeting on Nuclear Technology (AMNT)– Workshop Young Scientists, Berlin, Deutschland, May 7-8, 2019

  • Song, M.Q., Cheng, X.,2019. Heat transfer analysis of trans-critical pressure transient. AMNT-2019,May 7-8, 2019,Berlin,Germany.

  • Aurelian F. Badea, Meng Zhao, Xu Cheng. Heat Transfer Predictions for Supercritical Water Flowing in Different Geometries, NUTHOS-12, Qingdao, China, October 14-18, 2018.

  • Schenk M. CFD Analysis of Liquid Metal Pumps, German CFD Meeting, München, Deutschland; 6.-7. März 2018.

  • Yu, D., and Cheng, X. (2018). Verification of Proposed Post-Dryout Heat Transfer Model. 49. Jahrestagung Kerntechnik / 49th Annual Meeting on Nuclear Technology (AMNT 2018), Berlin, May 29-30.

  • L. Köckert, F. Feuerstein, D. Yu, D. Klingel, X. Cheng, “Experimental Study of Post-Dryout Heat Transfer and Rewetting in an R-134a Cooled Vertical Tube at Comparable Water-Cooled Reactor Pressure Conditions”, 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, October 14-18, 2018

  • Schenk M. CFD Analysis of Centrifugal Liquid Metal Pumps, 49th Annual Meeting on Nuclear Technology – Workshop Young Scientists, Berlin, Deutschland, 29-30 Mai 2018

  • Schenk M., Cheng X. CFD Analysis of Wall Shear Stress and Recirculation in Centrifugal Liquid Metal Pumps 12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-12), Qingdao, China, 14.-18. Oktober 2018

  • F. Wang et al. Model assessment of condensate droplet motion on inclined containment structure surface, NUTHOS12, 14-18 October, 2018, Qingdao, China.

  • M. Zhao, A.F. Badea, F. Feuerstein, X. Cheng. Assessment of experimental data of heat transfer to supercritical water in tubes, NURETH-17 conference paper, Sep 3-8, 2017.

  • James J. Peltz, Madalina C. Badea, Dan G. Cacuci, and Aurelian F. Badea. Predictive Modeling of a Paradigm Spent Fuel Dissolver, 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016) San Francisco, CA, April 17-20, 2016

  • Zhao, M., Yang, Q.R., Gu, H.Y., Li, H.B., Cheng, X., 2015. Experimental study on heat transfer of supercritical water flowing upward in 2 2 rod bundles, 46th Annual Meeting on Nuclear Technology, May 5th-7th, 2015, Berlin, Germany.

  • Meyer, S., Otic, I., Cheng, X., 2015. Phase-Field Modeling of Binary Eutectic Alloy Solidification with Convection, 16th International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH-16), Chicago, USA, August 30 - September 4

  • Dan G. Cacuci, James J. Peltz, Aurelian F. Badea, and Madalina C. Badea. Spent Fuel Dissolver Predictive Modeling: I. Application of the Adjoint Sensitivity Analysis Methodology for Nonlinear Systems with Operator-Type Responses, ANS Winter Meeting, Washington, DC, US, November 8-12, 2015.

  • James J. Peltz, Aurelian F. Badea, Madalina C. Badea and Dan G. Cacuci. Spent Fuel Dissolver Predictive Modeling: II. Uncertainty Reduction via Experimental Data Assimilation, ANS Winter Meeting, Washington, DC, US, November 8-12, 2015.

  • Sonntag, M., Cheng, X., 2015. CFD Model for Simulation of Subcooled Nucleate Flow Boiling and Coupling with STH-Code for Analysis of IVR Cool Ability, International Congress on Advances in Nuclear Power Plants, ICAPP 2015, Nice, France, May 3-6, 2015

  • Otic, I., Chai, X., Cheng, X., 2014. Pseudo-transient simulation of turbulent mixing in a rectangular channel, Proceedings of ICONE22, 2014

  • Otic, I., 2014. One equation subgrid model for turbulent convection, Proceedings of NUTHOS-10, 2014

  • Badea, A.F., Cacuci, D.G., Badea, M.C., 2014. Thermal Solar Collector Predictive Modeling: II. Data Assimilation, Model Calibration, and Best-Estimate Predictions with Reduced Uncertainties, ANS Meeting, Anheim, US, November 9-13, 2014.

  • Badea, A.F., Cacuci, D.G., Badea, M.C., 2013. Uncertainty Reduction in Calibrated FLICA4 Thermal-Hydraulics Computational Predictions Following Assimilation of Multiple BFBT Benchmark Experimental Data, The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-15, Pisa, Italy, May 12-15, 2013

  • Badea, A.F., Cacuci, D.G., Badea, M.C., 2013. Uncertainty Reduction in Coupled Neutron-Kinetics / Thermal-Hydraulics Computational Predictions Following Assimilation of BWR-TT Benchmark Experimental Data, The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-15, Pisa, Italy, May 12-15, 2013