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Veröffentlichungen seit 2013

Zeitschriften

 

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

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

Chai, X.,  Cheng, X., 2015. Wake acceleration effect on spherical bubbles aligned in-line, Progress in Nuclear Energy, 2015, 80: 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

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

 

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

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

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

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

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 22 rod bundles, 46th Annual Meeting on Nuclear Technology, May 5th-7th, 2015, Berlin, Germany.