Transient boiling flow in 5 × 5 rod bundle under non-uniform rapid heating

2018 ◽  
Vol 340 ◽  
pp. 447-456 ◽  
Author(s):  
Hiroki Takiguchi ◽  
Masahiro Furuya ◽  
Takahiro Arai ◽  
Kenetsu Shirakawa
Keyword(s):  
Rapid Heating ◽  
Rod Bundle ◽  
Boiling Flow ◽  
Transient Boiling

scholarly journals Multi-dimensional void fraction measurement of transient boiling two-phase flow in a heated rod bundle

2015 ◽  
Vol 2 (5) ◽  
pp. 15-00163-15-00163 ◽  
Author(s):  
Takahiro ARAI ◽  
Masahiro FURUYA ◽  
Taizo KANAI ◽  
Kenetsu SHIRAKAWA ◽  
Yoshihisa NISHI
Keyword(s):  
Void Fraction ◽  
Two Phase Flow ◽  
Phase Flow ◽  
Two Phase ◽  
Rod Bundle ◽  
Fraction Measurement ◽  
Transient Boiling

Numerical Solution for Transient Conjugate Two-Phase Heat Transfer With Heat Generation in the Pipe Wall

2002 ◽  
Vol 124 (6) ◽  
pp. 1213-1218 ◽  
Author(s):  
Yuri V. Fairuzov ◽  
Hector Arvizu
Keyword(s):  
Heat Transfer ◽  
Numerical Solution ◽  
Heat Generation ◽  
Two Phase ◽  
Convective Boiling ◽  
Wall Superheat ◽  
Boiling Flow ◽  
Rigorous Model ◽  
Two Phase Heat Transfer ◽  
Transient Boiling

A method developed earlier for modeling conjugate two-phase heat transfer in flashing flows was used to obtain a numerical solution for transient boiling flow in heated pipes or channels. Two criteria of applicability of the solution obtained were proposed and numerically tested using a more rigorous model, which accounts for the effects of heat conduction with heat generation in the wall and forced convective boiling. The solution obtained provides a simple and reliable alternative to more rigorous methods for modeling transient two-phase flow in heated channels when the material of the wall bounding the flow has a high thermal conductivity and the wall superheat is small.

Transient boiling flow instabilities in a multi-channel upflow system

1977 ◽  
Vol 10 (3) ◽  
pp. 175-188 ◽  
Author(s):  
S. Kakaç ◽  
T. N. Veziroğlu ◽  
N. Özboya ◽  
S. S. Lee
Keyword(s):  
Flow Instabilities ◽  
Boiling Flow ◽  
Transient Boiling

CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle

Kerntechnik ◽  
2021 ◽  
Vol 86 (1) ◽  
pp. 24-32
Author(s):  
B. Ren ◽  
Y. Dang ◽  
F. J. Gan ◽  
P. Yang
Keyword(s):  
Void Fraction ◽  
Cfd Simulation ◽  
Phase Distribution ◽  
Flow Boiling ◽  
Fluid Model ◽  
Three Dimensional ◽  
Spacer Grid ◽  
Pressurized Water ◽  
Rod Bundle ◽  
Boiling Flow

Abstract This paper describes the computational fluid dynamics (CFD) methodology to simulate the boiling flow in a typical Pressurized Water Reactor (PWR) 5 ⨯ 5 rod bundle. The method includes the Eulerian-Eulerian two-fluid model coupled with the improved wall heat partitioning model. The NUPEC PWR Subchannel and Bundle Test (PSBT) International Benchmark are used for validation. The simulated surface averaged void fraction agree well with the experimental data, which indicate the promising application of the present method for modeling the boiling flow in the fuel rod bundle. The main emphasis of current research has been given to the analysis of the phase distribution around and downstream the spacer grid, the effect of the spacer grid structure, including the mixing vanes, the springs and the dimples on the void fraction distribution is investigated. The findings can contribute to a better understanding of three dimensional flow boiling characteristics and can be used to assist in optimizing the spacer grid.

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