A numerical analysis has been performed to simulate the transient thermal-hydraulic response to a main steam line break (MSLB) for the secondary side of a steam generator (SG) model equipped with a venturi-type SG outlet flow restrictor at a pressurized water reactor (PWR) plant. To investigate the effects of the flow restrictor on the thermal-hydraulic response of SG to the MSLB, numerical calculation results for the SG model equipped with the flow restrictor are compared to those obtained for an SG model without the restrictor. Both analysis models contain internal structures. The present computational fluid dynamics (CFD) model has been examined by comparing to a simple analytical model. It is confirmed from the comparison that the CFD model simulates the transient response of the SG secondary to the MSLB physically plausibly and minutely. Based on the CFD analysis results for both cases with or without the restrictor, it is seen that the intensities of the steam velocity and dynamic pressure are considerably attenuated in the SG model equipped with the restrictor comparing to the case in the SG model without the restrictor.

References

References
1.
Shier
,
W. G.
, and
Levine
,
M. M.
,
1980
, “
PWR Steam Line Break Analysis Assuming Concurrent Steam Generator Tube Rupture
,”
ANS/ASME
Topical Meeting on Reactor Thermal-Hydraulics
,
Saratoga, NY
, Oct. 9, Paper No. CONF-801002-9
2.
Gallardo
,
S.
,
Querol
,
A.
, and
Verdú
,
G.
,
2012
, “
Simulation of a Main Steam Line Break With Steam Generator Tube Rupture Using Trace
,”
PHYSOR 2012
,
American Nuclear Society
,
Knoxville, TN
, Apr. 15–20, pp.
2131
2144
.
3.
Gallardo
,
S.
,
Querol
,
A.
, and
Verdú
,
G.
,
2013
, “
Improvements in the Simulation of a Main Steam Line Break With Steam Generator Tube Rupture
,”
Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo
,
Paris, France
, Oct. 27–31, Paper No. 05104.
4.
Kalra
,
S.
, and
Adams
,
G.
,
1980
, “
Thermal Hydraulics of Steam Line Break Transients in Thermal Reactors—Simulation Experiments
,”
ANS
International Conference, American Nuclear Society
,
Washington, DC
, Nov. 17–21, Vol.
35
, Paper No. CONF-801107.
5.
Wolf
,
L.
,
1982
, “
Experimental Results of Coupled Fluid–Structure Interactions During Blowdown of the HDR-Vessel and Comparisons With Pre- and Post-Test Predictions
,”
Nucl. Eng. Des.
,
70
(
3
), pp.
269
308
.
6.
Tinoco
,
H.
,
2002
, “
Three-Dimensional Modeling of a Steam-Line Break in a Boiling Water Reactor
,”
Nucl. Sci. Eng.
,
140
(
2
), pp.
152
164
.
7.
Joo
,
H. G.
,
Jeong
,
J.-J.
,
Cho
,
B.-O.
,
Lee
,
W. J.
, and
Zee
,
S. Q.
,
2003
, “
Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code
,”
Nucl. Technol.
,
142
(
2
), pp.
166
179
.
8.
Hamouda
,
O.
,
Weaver
,
D. S.
, and
Riznic
,
J.
,
2013
, “
Commissioning Tests for an Experimental Study of Steam Generator Tube Loading During Blowdown
,”
ASME
Paper No. PVP2013-97809.
9.
Hamouda
,
O.
,
Weaver
,
D. S.
, and
Riznic
,
J.
,
2014
, “
Instrumentation Development and Validation for an Experimental Study of Steam Generator Tube Loading During Blowdown
,”
ASME
Paper No. PVP2014-28137.
10.
Jo
,
J. C.
, and
Moody
,
F. J.
,
2015
, “
Transient Thermal-Hydraulic Responses of the Nuclear Steam Generator Secondary Side to a Main Steam Line Break
,”
ASME J. Pressure Vessel Technol.
,
137
(
4
), p.
041301
.
11.
Jo
,
J. C.
,
2015
, “
Thermal-Hydraulic Response of the Secondary Side of a PWR Steam Generator With an Internal Structure to a Main Steam Line Break
,”
ASME
Paper No. PVP2015-45092.
12.
Menter
,
F. R.
,
1994
, “
Two Equation Eddy-Viscosity Turbulence Models for Engineering Applications
,”
AIAA J.
,
32
(
8
), pp.
1598
1604
.
13.
ANSYS
,
2012
,
ANSYS CFX User's Guide-14
,
ANSYS, Inc.
,
New York
.
14.
Jo
,
J. C.
,
Lee
,
S. K.
,
Kim
,
W. S.
,
Shin
,
W. K.
,
Kim
,
H. Y.
, and
Ha
,
J. T.
,
1992
, “
A Study on the Thermal-Hydraulic and Flow-Induced Tube Vibration Analysis of Nuclear Steam Generators
,” Korea Institute of Nuclear Safety, Technical Report No. KINS/AR-198.
15.
Moody
,
F. J.
,
1990
,
Introduction to Unsteady Thermofluid Mechanics
,
Wiley
,
New York
.
16.
Shapiro
,
A.
,
1953
,
The Dynamics and Thermodynamics of Compressible Fluid Flow
, Vol.
1
,
Wiley
,
New York
.
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