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Dive into the research topics where Yanfei Rao is active.

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Featured researches published by Yanfei Rao.


Journal of Nuclear Engineering and Radiation Science | 2017

Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries

Attila Kiss; Andrey Churkin; Darwan S. Pilkhwal; Abhijeet M. Vaidya; Walter Ambrosini; Andrea Pucciarelli; Krishna Podila; Yanfei Rao; Laurence Leung; Chen Yuzhou; Mark Anderson; Meng Zhao

Two computational fluid dynamic (CFD) benchmarks have been performed to assess the prediction accuracy and sensitivity of CFD codes for heat transfer in different geometries. The first benchmark focused on heat transfer to water in a tube (first benchmark), while the second benchmark covered heat transfer to water in two different channel geometries (second benchmark) at supercritical pressures. In the first round with the experimental data unknown to the participants (i.e., blind calculations), CFD calculations were conducted with initial boundary conditions and simpler CFD models. After assessment against measurements, the calculations were repeated with the refined boundary conditions and material properties in the follow-up calculation phase. Overall, the CFD codes seem to be able to capture the general trend of heat transfer in the tube and the annular channel but further improvements are required in order to enhance the prediction accuracy. Finally, sensitivity analyses on the numerical mesh and the boundary conditions were performed. It was found that the prediction accuracy has not been improved with the introduction of finer meshes and the effect of mass flux on the result is the strongest among various investigated boundary conditions. [DOI: 10.1115/1.4038162]


Annals of Nuclear Energy | 2016

CFD modelling of turbulent flows through 5 × 5 fuel rod bundles with spacer-grids

Krishna Podila; Yanfei Rao


Journal of Nuclear Engineering and Radiation Science | 2016

A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle

M. Rohde; J. W. R. Peeters; Andrea Pucciarelli; Attila Kiss; Yanfei Rao; E. N. Onder; P. Muehlbauer; A. Batta; M. Hartig; Vijay Chatoorgoon; Roman Thiele; Stavros Tavoularis; D.R. Novog; D. Mcclure; Malwina Gradecka; K. Takase


Nuclear Engineering and Design | 2016

CFD modelling of supercritical water flow and heat transfer in a 2 × 2 fuel rod bundle

Krishna Podila; Yanfei Rao


Journal of Nuclear Engineering and Radiation Science | 2015

Assessment of Computational Tools in Support of Heat-Transfer Correlation Development for Fuel Assembly of Canadian Supercritical Water-Cooled Reactor

Laurence K.H. Leung; Yanfei Rao; Krishna Podila


Annals of Nuclear Energy | 2018

Estimation of appendage pressure-loss coefficients for fuel rod bundles using computational fluid dynamics

Krishna Podila; Yanfei Rao


Journal of Nuclear Engineering and Radiation Science | 2017

Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

Krishna Podila; Yanfei Rao


Annals of Nuclear Energy | 2017

Effect of power variations across a fuel bundle and within a fuel element on fuel centerline temperature in PHWR bundles in uncrept and crept pressure tubes

E.N. Onder; D. Roubtsov; Yanfei Rao; B. Wilhelm


Annals of Nuclear Energy | 2017

The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannels

N. Hammouda; Yanfei Rao


Journal of Supercritical Fluids | 2016

Assessment of subchannel code ASSERT-PV for supercritical applications

Yanfei Rao; E.N. Onder; K. Podila

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Krishna Podila

Chalk River Laboratories

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Attila Kiss

Budapest University of Technology and Economics

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E.N. Onder

Chalk River Laboratories

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E. N. Onder

Chalk River Laboratories

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K. Podila

Chalk River Laboratories

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J. W. R. Peeters

Delft University of Technology

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