Bau-Shei Pei

National Tsing Hua University — Taiwan

Engineering · Physical Sciences

15h-index608citations53works0.02yr avg
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Research Topics

Nuclear Engineering Thermal-Hydraulics(21), Nuclear reactor physics and engineering(18), Heat Transfer and Boiling Studies(17), Fluid Dynamics and Mixing(13), Heat Transfer and Optimization(10)

Publications53 total

Experimental investigation on local/global void distribution of air-water two-phase flow in a 3 × 3 rod bundle channel under low-flow conditions
International Journal of Heat and Fluid Flow·2020· 8 cited
Experimental Investigation for Flow Regime Identification Using Probability Density Function of Void Fraction Signals
Journal of Fluids Engineering·2020· 7 cited
The RESRAD Code Applications for Radiological Safety Analysis of Nuclear Power Plants Decommissioning
Transactions American Geophysical Union·2019
RADIOLOGICAL SAFETY ASSESSMENT OF DECOMMISSIONING NUCLEAR POWER PLANTS USING THE RESRAD CODE
The Proceedings of the International Conference on Nuclear Engineering (ICONE)·2019Open Access
Feasibility study for dispersed bubbly flow and other flow patterns spectrum boundary by probability density function
2018
Effect of Head Loss on Flow Rate of Spray System and Containment Pressure
2017
A CHF Correlation and Flow Pattern Observation on a Downward-Facing Boiling Surface
2017
Experimental investigation and identification of the transition boundary of churn and annular flows using multi-range differential pressure and conductivity signals
Applied Thermal Engineering·2016· 15 cited
Numerical analysis and experimental validation of heat transfer characteristic for flat-plate solar air collector
Applied Thermal Engineering·2016· 30 cited
Implementation and Assessment of Moody Homogeneous Equilibrium Critical Flow Model of RELAP5-3D
Nuclear Science and Engineering·2015
Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident
Annals of Nuclear Energy·2015· 53 cited
Flow impinging effect of critical heat flux and nucleation boiling heat transfer on a downward facing heating surface
Kerntechnik·2015· 11 cited
The development of a three-dimensional transient CFD model for predicting cooling ability of spent fuel pools
Applied Thermal Engineering·2012· 48 cited
A thermodynamic analysis of high temperature gas-cooled reactors for optimal waste heat recovery and hydrogen production
Applied Energy·2012· 24 cited
ICONE19-43445 Investigating Thermal-Hydraulic Characteristic of Molten Fluoride Salt in A Circular Pipe Using A CFD Methodology
The Proceedings of the International Conference on Nuclear Engineering (ICONE)·2011Open Access
Simulating the Thermal-Hydraulic Characteristics for the Molten Salt in a Round Tube Using CFD
Transactions of the American Nuclear Society·2010
Pressurized water reactor (PWR) hot-leg streaming
Nuclear Engineering and Design·2010· 13 cited
Pressurization transient analyses of the Lungmen ABWR plant using RETRAN-02
Nuclear Engineering and Design·2010· 2 cited
Effect of automatic recirculation flow control on the transient response for Lungmen ABWR plant
Nuclear Engineering and Design·2009· 2 cited
Power Uprate Impact Evaluations on Waste Heat of Nuclear Power Plants in Taiwan
Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems·2009· 1 cited
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Frequent Co-authors

Tzu‐Chen Hung(11), Yuh-Ming Ferng(11), Wei-Keng Lin(7), Ge‐Ping Yu(6), Yen-Shu Chen(5), Yung-Shin Tseng(5), Wen-Shan Lin(4), Chien‐Hsiung Lee(4), Yin-Pang Ma(4), Yih-Yun Hsu(4), Shao-Wen Chen(4), Min-Song Lin(4), Jin-Der Lee(4), Huai-En Hsieh(4), Chunkuan Shih(4), Kuo-Hsiang Chien(3), Chi‐Chuan Wang(3), Nien‐Mien Chung(3), Feng-Jiun Kuo(3), Zhen-Yu Hung(2)