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Article

Validation of three-dimensional simulation method for two-phase flow in triangular-pitch tube bundle in secondary side of steam generators on porous two-fluid model

, , , , , , , & show all
Pages 78-95 | Received 08 Jan 2021, Accepted 07 Jul 2021, Published online: 19 Aug 2021
 

ABSTRACT

In the design process of a steam generator, a porous-media-approach computational code is utilized for simulating three-dimensional two-phase flow behavior in the secondary side of steam generators. For the design of next-generation steam generators, the advanced thermal-hydraulic analysis code based on the two-fluid model has been developed by implementing constitutive equations into the ANSYS fluent. For code validation, experiments using two-phase simulant fluids were performed to collect data in a simulated steam generator with a triangular tube array. The simulant two-phase flow system selected in the experiment was an adiabatic sulfur hexafluoride gas and liquid ethanol system, which allowed us to achieve the density ratio of prototypic steam-water flow with low pressure (=0.68 MPa). In the experiment, void fraction and gas–liquid interfacial velocity distributions along U-tubes were measured. The code validation was conducted by analyzing code predictions for measured distributions of void fraction and interfacial velocity under prototypic full load and partial load conditions, i.e., 50–80% flow rate conditions. Their bias and random errors were evaluated. The reasonable random errors demonstrated the validity of the newly developed code based on the two-fluid model in terms of predictions of void fraction and interfacial velocity in the secondary side of steam generators.

Nomenclature

A=

structural surface area

ai=

interfacial area concentration

C=

parameter

Cbend=

constant (=1.7)

CD=

drag coefficient acting on gas phase

CD,CF=

drag coefficient for cross-flow

CvV=

covariance

DH=

hydraulic equivalent diameter

D0=

rod diameter

eV=

volume porosity

F=

external force per unit volume acting on two-phase flow

Gi=

two-phase mixture mass flux in i-th injection unit

GR=

two-phase mixture mass flux in riser section

f=

friction factor

g=

gravitational acceleration

I=

unit tensor

j=

mixture volumetric flux

M=

generalized interfacial drag force per unit volume

Mi=

interfacial drag force per unit volume

Nt=

number of tube row

Pt=

smallest rod pitch

p=

pressure

R=

quantity

t=

time

VF=

free volume in a control volume

VT=

total control volume

v=

velocity

vi,SC=

interfacial velocity at the center of equilateral-triangle rod pattern

vr=

relative velocity

Greek symbol

α=

void fraction

αcrit=

critical void fraction

β=

volumetric flow fraction

Γ=

mass generation rate

Δl=

azimuthal distance

ΔP2ϕ,CF=

pressure drop due to form drag for two-phase cross-flow over horizontal heat transfer tubes

ΔP2ϕ,PF=

pressure drop due to wall friction for two-phase parallel flow along with vertical heat transfer tubes

Δρ=

density difference between gas and liquid phases

ρ=

density

σ=

surface tension

τ=

viscous stress

τT=

turbulent stress

ϕf=

two-phase multiplier by Chisholm’s correlation

ϕf0=

two-phase multiplier by Thom’s correlation

ψ=

variable

ω=

angle

Subscripts

f=

liquid

G=

gap

g=

gas

k=

k-phase

m=

mixture

rr=

-direction

S=

sub-channel

yy=

-direction

zz=

-direction

θθ=

-direction

=

approaching velocity

Mathematical operators

 V=

intrinsic phase average quantity

V=

void-fraction-weighted-mean quantity

=

phase average quantity

ˆ=

phase density-weighted mean quantity

Acknowledgments

The experimental and validation works in this study have been carried out as a Japanese government-subsidized R & D project, “The Safety Improvement of Nuclear Facilities,” with the participation of the Kansai Electric Power Co., Inc., Hokkaido Electric Power Co., Inc., Shikoku Electric Power Co., Inc., Kyushu Electric Power Co., Inc., The Japan Atomic Power Company, The Institute of Applied Energy, and Mitsubishi Heavy Industries, Ltd.

Disclosure statement

No potential conflict of interest was reported by the author(s).

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