Two-phase flow induced vibration in piping systems

S Miwa, M Mori, T Hibiki - Progress in Nuclear Energy, 2015 - Elsevier
Hydrodynamic force acting on the structures, pipes and various forms of objects can
generate destructive vibrations, and could cause acoustic and noise problems in industrial …

Full-scale numerical study on the flow characteristics and mal-distribution phenomena in SG steam-water separation system of an advanced PWR

D Fang, M Wang, Y Duan, J Li, G Qiu, W Tian… - Progress in Nuclear …, 2020 - Elsevier
The steam-water separation system is of great importance to ensuring the steam quality in a
PWR UTSG. In the present work, the full-scale three-dimensional CFD analysis is performed …

Migration–deposition coupling characteristics and influence of corrosion products on heat transfer in steam generators

D Mu, M Wang, J Zhang, W Tian, S Qiu… - Applied Thermal …, 2022 - Elsevier
Fouling on tube surfaces degrades the heat transfer characteristics of heat exchangers. The
objective of this study was to predict the distribution of deposits on the surface of heat …

Experimental investigations on single-phase convection and steam-water two-phase flow boiling in a vertical rod bundle

K Zhang, YD Hou, WX Tian, YQ Fan, GH Su… - … Thermal and Fluid …, 2017 - Elsevier
Single-phase convective heat transfer and steam-water two-phase flow boiling heat transfer
experiments have been carried out with a vertical seven-rod bundle at low flow conditions …

Internal two-phase flow induced vibrations: A review

SG Haile, E Woschke, GS Tibba, V Pandey - Cogent Engineering, 2022 - Taylor & Francis
Flow-induced vibration (FIV) is a common phenomenon observed in internal flows and is
frequently encountered in technical systems like process plants, nuclear plants, oil-piping or …

Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method

R Chen, M Tian, S Chen, W Tian, GH Su, S Qiu - Annals of Nuclear Energy, 2017 - Elsevier
Thermal-hydraulic performance in the reactor core was an essential factor in the nuclear
power plant design. In this study, we analyzed the three-dimensional (3-D) thermal-hydraulic …

Experimental study on flow boiling and circumferential non-uniform heat transfer characteristics in helically-coiled tube under coupled heat transfer conditions

H Wang, Q Xuan, H Lei, X Li, Z Li, H Li - Applied Thermal Engineering, 2025 - Elsevier
Helically-coiled tube steam generator has been widely used in nuclear reactor, energy
power, petrochemical and other systems. In the liquid metal reactor, the liquid metal on the …

CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger

J Ge, W Tian, S Qiu, GH Su - Nuclear Engineering and Design, 2018 - Elsevier
Passive residual heat removal heat exchanger (PRHR HX) is a key equipment in advanced
passive safety pressurized water reactors (PWRs), such as AP1000. Immerged in the In …

Non-uniform boiling heat transfer characteristics and calculation evaluation in U-tube Steam Generator tube bundle

Z Li, Y Yan, G Fan, X Zeng, S Hao, C Yan - Energy, 2024 - Elsevier
U-tube steam generator, as one of the core equipment in nuclear power plants, has radially
non-uniform heating on the secondary side, which complicates the progress of heat transfer …

Pressure drop characteristics of vertically upward flow in inclined rod bundles

K Zhang, WX Tian, YD Hou, YP Zhang, SZ Qiu… - … Thermal and Fluid …, 2016 - Elsevier
An experimental and theoretical research has been carried out for vertically upward two-
phase flow of air–water across staggered rod bundles having inclination angles of 0°, 45° …