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Dive into the research topics where Shanfang Huang is active.

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Featured researches published by Shanfang Huang.


2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference | 2012

Analytical Prediction of Turbulent Friction Factor in Circular Pipe Under Supercritical Conditions

Jinguang Zang; Xiao Yan; Shanfang Huang; Zejun Xiao; Yanping Huang

An analytical method was proposed for the prediction of the turbulent friction factor in a circular pipe under supercritical conditions. The friction factor equation was based on the new wall function by Van Direst transformation which is widely used in compressed flow. The law of the wall of two layers was used and integrated over the entire flow area to obtain the algebraic form of the turbulent friction factor. The new turbulent friction formula was first adjusted to Colebrook equation in isothermal flow at supercritical pressures. And then it was validated in heated supercritical flow by several existing correlations. Similar trends were found between them, which confirms the physical validity of the new frictional formula. The theoretical analysis also shows that the friction factor due to the variation of fluid property at supercritical pressures is mainly caused by the density and viscosity variation. In viscous sublayer, both the viscosity play the main role, while in turbulent sublayer, only the density do.Copyright


International Journal of Heat and Mass Transfer | 2013

Modeling and analysis of supercritical flow instability in parallel channels

Ting Xiong; Xiao Yan; Shanfang Huang; Junchong Yu; Yanping Huang


Annals of Nuclear Energy | 2017

Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF

Juanjuan Guo; Shichang Liu; Xiaotong Shang; Shanfang Huang; Kan Wang


Nuclear Engineering and Design | 2014

A method of extending subcritical heat transfer correlations to supercritical conditions

Jinguang Zang; Xiao Yan; Shanfang Huang; Xiaokang Zeng; Yongliang Li; Yanping Huang; Junchong Yu


Annals of Nuclear Energy | 2017

BEAVRS full core burnup calculation in hot full power condition by RMC code

Shichang Liu; Jingang Liang; Qu Wu; Juanjuan Guo; Shanfang Huang; Xiao Tang; Zeguang Li; Kan Wang


Annals of Nuclear Energy | 2014

A general method for developing friction factor formulas under supercritical conditions and in different geometries

Jinguang Zang; Xiao Yan; Shanfang Huang; Xiaokang Zeng; Yongliang Li; Yanping Huang; Junchong Yu


Nuclear Engineering and Design | 2018

Versatility and stabilization improvements of full core neutronics/thermal-hydraulics coupling between RMC and CTF

Juanjuan Guo; Shichang Liu; Xiaotong Shang; Qicang Shen; Xiaoyu Guo; Shanfang Huang; Kan Wang; Xiaoming Chai


Annals of Nuclear Energy | 2018

The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention

Qiang Hu; Xiao Yan; Shanfang Huang; Junchong Yu


Annals of Nuclear Energy | 2018

A critical heat flux model for saturated flow boiling on the downward curved heated surface

Qiang Hu; Xiao Yan; Shanfang Huang; Junchong Yu


Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues | 2017

Public Acceptance of Spent Fuel Reprocessing Project

Zijian Wang; Shanfang Huang; Xiaoyu Guo; Kan Wang

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Qu Wu

Tsinghua University

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