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The Advanced Multi-phase Flow Laboratory, Department of Mechanical and Nuclear Engineering
Vertical-Downward Elbow Restriction on Two-Phase Flow
Sponsored by Toshiba-Westinghouse Fellows Program
OBJECTIVE: To investigate the geometric effects of a vertical-downward elbow on
two-phase flow by comparing single-phase CFD simulation and two-phase flow data.
SIGNIFICANCE
SUMMARY
• Void fraction has a single-peaked distribution which dissipates
after a vertical-downward elbow.
• Void fraction distribution shows weak relationship with
secondary flow downstream of vertical-downward elbow
• Vertical-downward elbow shows dramatically different trends
than vertical-upward; thus elbow-specific models are required
RESULTS
METHODS AND FACILITY
FUTURE WORK
• Obtain additional data at different locations and flow rates for database
• Develop predictive models for two-phase flow restrictions
• Implement new models to reactor thermal-hydraulic system analysis code
• In disaster situations, two-phase flow is induced during a loss of coolant
accident (LOCA) when a leak or pipe break depressurize the primary loop of
pressurized water reactors (PWRs).
• Little is known about two-phase flow restrictions; database creation vital
• Improve reactor thermal-hydraulic codes for enhanced safety analysis by
implementing models created from database of restricted flow
Single-Phase Simulation
● Counter-rotating vortices
produce swirling
● Low velocity water emanates
from inner wall; high velocity
water concentrated near
outer wall.
Two-Phase Experiment
● Single peak of void fraction
along the inner wall.
● Void fraction ‘ridge’ along
pipe wall at 0D
● Partial dissipation of peak
at 3D
● Evidence of secondary
bimodal peaking at 3D
● Negligible bubble
entrainment by swirling
for vertical-downward
elbow.
● Upstream conditions
and pressure
distribution cause
single-peak void fraction
distribution
● Previous research for
vertical-pward elbow
shows bimodal peaking
as bubbles are entrained
in secondary flow. (jf
=3.00 m/s; jg, atm =0.14
m/s)
Comparison
Test Facility
CFD Methods
Experimental Methods
● ANSYS CFX computational fluid
dynamics solver used for analysis
● Entire loop geometry simulated
● RNG k-ε turbulence model
● High quality mesh
● 50.8 mm ID acrylic test
section
● 90° glass elbows
● Development Length:
○ Vertical: ~60D (~3 m)
○ Horizontal: ~180D (~9 m)
Four-Sensor Conductivity Probe
Measurement principle
Kim et al., 2014
120 data points per cross-section
Andrew Hardison, Robert Morris University Philip Graybill, Grove City College
Mesh
cross-section
Probe captures time-averaged
local two-phase flow parameters
(Nb, fb, Vb, α, ai, & Dsm)
Four-Sensor Conductivity
Probe Schematic
● Adiabatic air-water
● Dual injection
● 24 measurement
locations
Measurement PointsVolumetric liquid flux (jf ) : 4.00 m/s
Volumetric gas flux (jg, atm ) : 0.23 m/s
L=3DL=0D
Bulk velocity (Ubulk ) : 4.00 m/s
Void
Fraction L=0D L=3D
Previous
Work
Vertical-UpwardVertical-Downward
L=3D
L=0D
Previous
Work
(Yadav, 2013)

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Graybill-Hardison Final Poster

  • 1. The Advanced Multi-phase Flow Laboratory, Department of Mechanical and Nuclear Engineering Vertical-Downward Elbow Restriction on Two-Phase Flow Sponsored by Toshiba-Westinghouse Fellows Program OBJECTIVE: To investigate the geometric effects of a vertical-downward elbow on two-phase flow by comparing single-phase CFD simulation and two-phase flow data. SIGNIFICANCE SUMMARY • Void fraction has a single-peaked distribution which dissipates after a vertical-downward elbow. • Void fraction distribution shows weak relationship with secondary flow downstream of vertical-downward elbow • Vertical-downward elbow shows dramatically different trends than vertical-upward; thus elbow-specific models are required RESULTS METHODS AND FACILITY FUTURE WORK • Obtain additional data at different locations and flow rates for database • Develop predictive models for two-phase flow restrictions • Implement new models to reactor thermal-hydraulic system analysis code • In disaster situations, two-phase flow is induced during a loss of coolant accident (LOCA) when a leak or pipe break depressurize the primary loop of pressurized water reactors (PWRs). • Little is known about two-phase flow restrictions; database creation vital • Improve reactor thermal-hydraulic codes for enhanced safety analysis by implementing models created from database of restricted flow Single-Phase Simulation ● Counter-rotating vortices produce swirling ● Low velocity water emanates from inner wall; high velocity water concentrated near outer wall. Two-Phase Experiment ● Single peak of void fraction along the inner wall. ● Void fraction ‘ridge’ along pipe wall at 0D ● Partial dissipation of peak at 3D ● Evidence of secondary bimodal peaking at 3D ● Negligible bubble entrainment by swirling for vertical-downward elbow. ● Upstream conditions and pressure distribution cause single-peak void fraction distribution ● Previous research for vertical-pward elbow shows bimodal peaking as bubbles are entrained in secondary flow. (jf =3.00 m/s; jg, atm =0.14 m/s) Comparison Test Facility CFD Methods Experimental Methods ● ANSYS CFX computational fluid dynamics solver used for analysis ● Entire loop geometry simulated ● RNG k-ε turbulence model ● High quality mesh ● 50.8 mm ID acrylic test section ● 90° glass elbows ● Development Length: ○ Vertical: ~60D (~3 m) ○ Horizontal: ~180D (~9 m) Four-Sensor Conductivity Probe Measurement principle Kim et al., 2014 120 data points per cross-section Andrew Hardison, Robert Morris University Philip Graybill, Grove City College Mesh cross-section Probe captures time-averaged local two-phase flow parameters (Nb, fb, Vb, α, ai, & Dsm) Four-Sensor Conductivity Probe Schematic ● Adiabatic air-water ● Dual injection ● 24 measurement locations Measurement PointsVolumetric liquid flux (jf ) : 4.00 m/s Volumetric gas flux (jg, atm ) : 0.23 m/s L=3DL=0D Bulk velocity (Ubulk ) : 4.00 m/s Void Fraction L=0D L=3D Previous Work Vertical-UpwardVertical-Downward L=3D L=0D Previous Work (Yadav, 2013)