The heat transfer of water in a vertically heated tube at 24.52 MPa is numerically simulated by computational fluid dynamics software of FLUENT. The IAPWS-IF97 formulation is applied to obtain the water properties, which vary substantially at supercritical condition. The two-dimensional axi-symmetric model using RNG k-ε turbulence model with enhanced wall treatment gives fine prediction of wall temperature and heat transfer coefficient. The mesh size near the wall adapted smaller when at high heat fluxes for the accuracy of computed results. The wall heat fluxes were set to be 233, 698, 930 and 1100 kW/m2 to match the simulation with experiment performed by Yamagata. It is found that k-ε turbulence model with enhanced wall treatment can give outstanding prediction of heat transfer enhancement and heat transfer deterioration. The heat transfer coefficient value reaches a maximum near the pseudocritical point and it decreases with increase of heat flux.
Skip Nav Destination
2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5580-5
PROCEEDINGS PAPER
Numerical Simulation of Supercritical Water Heat Transfer in the Vertically Heated Tube Available to Purchase
Feng Wang,
Feng Wang
Chongqing University, Chongqing, China
Search for other works by this author on:
Shijun Zhang,
Shijun Zhang
China Nuclear Power Engineering Co., Ltd., Shenzhen, Guangdong, China
Search for other works by this author on:
Xue Qin
Xue Qin
Chongqing University, Chongqing, China
Search for other works by this author on:
Feng Wang
Chongqing University, Chongqing, China
Bo Cui
Chongqing University, Chongqing, China
Shijun Zhang
China Nuclear Power Engineering Co., Ltd., Shenzhen, Guangdong, China
Xue Qin
Chongqing University, Chongqing, China
Paper No:
ICONE21-16158, V003T10A035; 5 pages
Published Online:
February 7, 2014
Citation
Wang, F, Cui, B, Zhang, S, & Qin, X. "Numerical Simulation of Supercritical Water Heat Transfer in the Vertically Heated Tube." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. Chengdu, China. July 29–August 2, 2013. V003T10A035. ASME. https://doi.org/10.1115/ICONE21-16158
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes
ASME J of Nuclear Rad Sci (July,2016)
High-Flux Thermal Management With Supercritical Fluids
J. Heat Transfer (December,2016)
Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes
ASME J of Nuclear Rad Sci (July,2016)
Related Chapters
Numerical Simulation Research on a Fixed Bed Gasifier
International Conference on Information Technology and Management Engineering (ITME 2011)
List of Commercial Codes
Introduction to Finite Element, Boundary Element, and Meshless Methods: With Applications to Heat Transfer and Fluid Flow
CFD Simulations of a Mixed-flow Pump Using Various Turbulence Models
Mixed-flow Pumps: Modeling, Simulation, and Measurements