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Article

Modeling of distribution parameters for upward steam-water boiling flows in subchannels of a vertical rod bundle

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Pages 1481-1499 | Received 17 Oct 2022, Accepted 04 Apr 2023, Published online: 19 Jul 2023
 

ABSTRACT

In simulations of two-phase flow behavior in nuclear reactors, subchannel analysis codes are often used to evaluate the void fraction within a BWR fuel bundle in detail. When solving the momentum conservation equation averaged over a subchannel cross-section for upward two-phase flows, the distribution parameter is required to consider the void fraction and velocity distributions in the subchannel cross-section. In this paper, constitutive equations were developed for the distribution parameters for dispersed two-phase flows applicable to the inner, edge, and corner subchannels, which are typical subchannels in a fuel bundle. The distribution parameters could be calculated by giving the void fraction and the velocity distribution. Therefore, the distribution parameters were evaluated and modeled as a function of the geometrical parameters by assuming the void fraction and velocity distributions with bulk and subcooled boiling for each subchannel type. The developed constitutive equations were evaluated by comparing them with the distribution parameters estimated based on the NUPEC rod bundle void fraction test data. The developed distribution parameter model was implemented into the subchannel analysis code NASCA and compared with the measured cross-sectional average void fraction of the NUPEC rod bundle void fraction test data. In comparison with the original NASCA code, which assumed the distribution parameter to be unity, the improved NASCA with the distribution parameter model decreased the mean error of the measured cross-sectional average void fraction to less than half of the result of the original NASCA code, both in absolute and relative differences.

GRAPHICAL ABSTRACT

Nomenclature

a=

coefficient

Ac=

flow area

Awp=

bubble layer area

ai=

interfacial area concentration

b=

exponent

C0=

distribution parameter

CD=

drag coefficient

D0=

rod diameter

j=

mixture volumetric flux

jc,p=

maximum mixture volumetric flux in a given radial direction of p-type subchannel

jc0,p=

maximum mixture volumetric flux within a p-type subchannel

k=

ratio of the gap between the rod and channel wall to the gap between rods

Mif=

interfacial drag force acting on liquid phase

Mig=

interfacial drag force acting on gas phase

md=

mean absolute error

mj=

exponent for volumetric flux distribution

mrel=

mean relative deviation

mrel,ab=

mean absolute relative deviation

mα=

exponent for void fraction distribution

P0=

rod pitch

P1=

distance from rod center to the wall of the flow channel

R0=

rod radius

Rc=

distance from the origin to the position where j=jc

Rp=

radius of round tube

r=

radial position from rod surface

sd=

standard deviation

vr=

relative velocity between gas and liquid phase

xwp=

bubble layer thickness

Greek symbols=
α=

void fraction

αc0,p=

void fraction at the center of a p-type subchannel

αwp=

void fraction at assumed square bubble layer

Λ=

the ratio of the subchannel distribution parameter to round tube distribution parameter

ψ=

shape factor

θ=

azimuthal position

θ0=

threshold angle for edge subchannel

θ′=

angle where the maximum value of mixture volumetric flux occurs

ρ=

density

Subscripts=
c=

corner subchannel

cal=

calculated value

e=

edge subchannel

exp=

measured value

f=

liquid phase

g=

gas phase

i=

interior subchannel

p=

subchannel type

rt=

round tube

=

asymptotic value

Acknowledgments

One of the authors (T. Hibiki) appreciates the support provided by the City University of Hong Kong (Project Number: 7005924).

Disclosure statement

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

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