Abstract
The thermal-hydraulic behavior of the flow in rod bundles has motivated numerous experimental and computational investigations. Previous studies have identified potential for accumulation of debris within the small subchannels of typical wire-wrapped assemblies with subsequent total or partial blockage of subchannel coolant flow. A test campaign was conducted to study the effects of localized blockages on the bundle averaged friction factor of a tightly packed wire-wrapped rod bundle. Blockages were installed within the bundle, and fluid pressure drop was measured across one wire pitch for a Reynolds number range of 500–17,200. The Darcy–Weisbach friction factor of the perturbed rod bundle geometry was compared with that of the unblocked bundle, as well as with the predictions of a well-established friction factor correlation. Differing effects based on blockage size and location for various flow regimes were studied. A number of conclusions can be made about the effects of the blockages on the friction factor, such as an increasing effect of the blockage on friction factor with an increase in Reynolds number, a change in flow behavior in the turbulent transition flow regime near Reynolds number 3000, differences in effect on friction factor for different types of subchannel blockage, and a nonlinear trend in friction factor variation with flow area impeded for edge subchannels. To this end, all data and quantified uncertainty produced in this study are made available for comparison and validation of advanced computational tools.
Issue Section:
Flows in Complex Systems
References
1.
Sahoo
,
K.
, and
Mohanty
,
A.
, 1991
, “
Turbulent Transport in Wall Subchannels and in Finite Rod Clusters
,” Int. J. Heat Fluid Flow
,
12
(2
), pp. 142
–149
.10.1016/0142-727X(91)90041-S2.
Piro
,
M.
,
Wassermann
,
F.
,
Grundmann
,
S.
,
Tensuda
,
B.
,
Kim
,
S. J.
,
Christon
,
M.
,
Berndt
,
M.
,
Nishimura
,
M.
, and
Tropea
,
C.
, 2017
, “
Fluid Flow Investigations Within a 37 Element CANDU Fuel Bundle Supported by Magnetic Resonance Velocimetry and Computational Fluid Dynamics
,” Int. J. Heat Fluid Flow
,
66
, pp. 27
–42
.10.1016/j.ijheatfluidflow.2017.04.0103.
Mikuž
,
B.
, and
Tiselj
,
I.
, 2017
, “
URANS Prediction of Flow Fluctuations in Rod Bundle with Split-Type Spacer Grid
,” Int. J. Heat Fluid Flow
,
64
, pp. 10
–22
.10.1016/j.ijheatfluidflow.2017.01.0084.
Shams
,
A.
,
Mikuž
,
B.
, and
Roelofs
,
F.
, 2018
, “
Numerical Prediction of Flow and Heat Transfer in a Loosely Spaced Bare Rod Bundle
,” Int. J. Heat Fluid Flow
,
73
, pp. 42
–62
.10.1016/j.ijheatfluidflow.2018.07.0065.
Rehme
,
K.
, 1967
, “
Geometry-Dependence of the Pressure Loss in Rod Bundles with Coiled Wire Spacers and Longitudinal Flow
,” Ph.D. thesis, University of Karlsruhe Germany, Karlsruhe, Germany.6.
Rehme
,
K.
, 1972
, “
Pressure Drop Performance of Rod Bundles in Hexagonal Arrangements
,” Int. J. Heat Mass Transfer
,
15
(12
), pp. 2499
–2517
.10.1016/0017-9310(72)90143-37.
Rehme
,
K.
, 1973
, “
Pressure Drop Correlations for Fuel Element Spacers
,” Nucl. Technol.
,
17
(1
), pp. 15
–23
.10.13182/NT73-A312508.
Reihman
,
T. C.
, 1969
, “An Experimental Study of Pressure Drop in Wire Wrapped FFTF Assemblies
.” Pacific Northwest Laboratory
, Richland, WA
, Report No. BNWL-1207.9.
Cheng
,
S.
, and
Todreas
,
N.
, 1984
, “
Constitutive Correlations for Wire-Wrapped Subchannel Analysis under Forced and Mixed Convection Conditions. Part 1.[LMFBR]
,” Ph.D. thesis,
Massachusetts Institute of Technology
, Cambridge, MA
.10.
Cheng
,
S.-K.
, and
Todreas
,
N. E.
, 1986
, “
Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles Friction Factors, Subchannel Friction Factors and Mixing Parameters
,” Nucl. Eng. Des.
,
92
(2
), pp. 227
–251
.10.1016/0029-5493(86)90249-911.
Chen
,
S.
,
Petroski
,
R.
, and
Todreas
,
N.
, 2013
, “
Numerical Implementation of the Cheng and Todreas Correlation for Wire Wrapped Bundle Friction Factors-Desirable Improvements in the Transition Flow Region
,” Nucl. Eng. Des.
,
263
, pp. 406
–410
.10.1016/j.nucengdes.2013.06.01212.
Chen
,
S.
,
Todreas
,
N.
, and
Nguyen
,
N.
, 2014
, “
Evaluation of Existing Correlations for the Prediction of Pressure Drop in Wire-Wrapped Hexagonal Array Pin Bundles
,” Nucl. Eng. Des.
,
267
, pp. 109
–131
.10.1016/j.nucengdes.2013.12.00313.
Bertocchi
,
F.
,
Rohde
,
M.
, and
Kloosterman
,
J.
, 2019
, “
Experimental Investigation on the Influence of Gap Vortex Streets on Fluid-Structure Interactions in Hexagonal Bundle Geometries
,” Int. J. Heat Fluid Flow
,
79
, p. 108443
.10.1016/j.ijheatfluidflow.2019.10844314.
Bertocchi
,
F.
,
Rohde
,
M.
, and
Kloosterman
,
J.
, 2019
, “
Understanding Migratory Flow Caused by Helicoid Wire Spacers in Rod Bundles: An Experimental and Theoretical Study
,” Int. J. Heat Fluid Flow
,
80
, p. 108491
.10.1016/j.ijheatfluidflow.2019.10849115.
Shaver
,
D. R.
,
Carasik
,
L. B.
,
Merzari
,
E.
,
Salpeter
,
N.
, and
Blandford
,
E.
, 2019
, “
Calculation of Friction Factors and Nusselt Numbers for Twisted Elliptical Tube Heat Exchangers Using nek5000
,” ASME Paper No. FEDSM2018-83477
.10.1115/1.404288916.
Yang
,
E. E.
,
Rahai
,
H. R.
, and
Nakayama
,
A.
, 1994
, “
Mean Pressure Distribution and Drag Coefficient of Wire-Wrapped Cylinders
,” ASME J. Fluids Eng.
,
116
(2
), pp. 376
–378
.10.1115/1.291028517.
Chun
,
M.-H.
, and
Seo
,
K.-W.
, 2001
, “
An Experimental Study and Assessment of Existing Friction Factor Correlations for Wire-Wrapped Fuel Assemblies
,” Ann. Nucl. Energy
,
28
(17
), pp. 1683
–1695
.10.1016/S0306-4549(01)00023-818.
Choi
,
S. K.
,
Choi
,
I. K.
,
Nam
,
H. Y.
,
Choi
,
J. H.
, and
Choi
,
H. K.
, 2003
, “
Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor
,” ASME J. Pressure Vessel Technol
,
125
(2
), pp. 233
–238
.10.1115/1.156507619.
Vassallo
,
P.
, and
Symolon
,
P.
, 2008
, “
Friction Factor Measurements in an Equally Spaced Triangular Array of Circular Tubes
,” ASME J. Fluids Eng.
,
130
(4
), p. 041105.10.1115/1.290381720.
Chang
,
S.-K.
,
Euh
,
D.-J.
,
Choi
,
H. S.
,
Kim
,
H.
,
Choi
,
S. R.
, and
Lee
,
H.-Y.
, 2016
, “
Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-Pin Rod Bundle for a Sodium-Cooled Fast Reactor
,” Nucl. Eng. Technol.
,
48
(2
), pp. 376
–385
.10.1016/j.net.2015.12.01321.
Genc¸Ay
,
S.
,
Tapucu
,
A.
,
Troche
,
N.
, and
Merilo
,
M.
, 1984
, “
Experimental Study of the Diversion Crossflow Caused by Subchannel Blockages. Part I: Experimental Procedures and Mass Flow Rates in the Channels
,” ASME J. Fluids Eng.
,
106
(4
), pp. 435
–440
.10.1115/1.324314322.
Tapucu
,
A.
,
Genc¸Ay
,
S.
,
Troche
,
N.
, and
Merilo
,
M.
, 1984
, “
Experimental Study of the Diversion Crossflow Caused by Subchannel Blockages. Part II: Pressures in the Channels and the Comparison of the COBRA III-C Predictions With Experimental Data
,” ASME J. Fluids Eng.
,
106
(4
), pp. 441
–447
.10.1115/1.324314423.
Teyssedou
,
A.
,
Tapucu
,
A.
, and
Camarero
,
R.
, 1992
, “
Blocked Flow Subchannel Simulation Comparison With Single-Phase Flow Data
,” ASME J. Fluids Eng.
,
114
(2
), pp. 205
–213
.10.1115/1.291001724.
Fontana
,
M. H.
,
Kress
,
T. S.
,
Parsly
,
T. S.
,
Thomas
,
D. G.
, and
Wantland
,
J. L.
, 1973
, “Effect of Partial Blockages in Simulated LMFBR Fuel Assemblies
,”
Oak Ridge National Laboratory (ORNL)
,
Oak Ridge, TN
, Report No. ORNL-TM-4324.25.
Fontana
,
M. H.
,
Thomas
,
D. G.
,
Kress
,
T. S.
, and
Wantland
,
J. L.
, 1975
, “Thermal-Hydraulic Effects of Partial Blockages in Simulated LMFBR Fuel Assemblies With Applications to the CRBR,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
, Report No. ORNL-TM-4779.26.
Han
,
J. T.
, 1977
, “Blockages in LMFBR Fuel Assemblies: A Review of Experimental and Theoretical Studies
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
, Report No. ORNL/TM-5839.27.
Han
,
J. T.
, and
Fontana
,
M. H.
, 1977
, “Blockages in LMFBR Fuel Assemblies: A Review
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
, Report No. Conf-771120-14.28.
Roelofs
,
F.
,
Gopala
,
V.
,
Chandra
,
L.
,
Viellieber
,
M.
, and
Class
,
A.
, 2012
, “
Simulating Fuel Assemblies With Low Resolution CFD Approaches
,” Nucl. Eng. Des.
,
250
, pp. 548
–559
.10.1016/j.nucengdes.2012.05.02929.
Di Piazza
,
I.
,
Magugliani
,
F.
,
Tarantino
,
M.
, and
Alemberti
,
A.
, 2014
, “
A CFD Analysis of Flow Blockage Phenomena in ALFRED LFR Demo Fuel Assembly
,” Nucl. Eng. Des.
,
276
, pp. 202
–215
.10.1016/j.nucengdes.2014.05.03330.
Raj
,
M. N.
,
Velusamy
,
K.
, and
Maity
,
R. K.
, 2016
, “
Thermal Hydraulic Investigations on Porous Blockage in a Prototype Sodium Cooled Fast Reactor Fuel Pin Bundle
,” Nucl. Eng. Des.
,
303
, pp. 88
–108
.10.1016/j.nucengdes.2016.04.00831.
Nguyen
,
T.
,
White
,
L.
,
Vaghetto
,
R.
, and
Hassan
,
Y.
, 2019
, “
Turbulent Flow and Vortex Characteristics in a Blocked Subchannel of a Helically Wrapped Rod Bundle
,” Exp. Fluids
,
60
(8
), p. 129
.10.1007/s00348-019-2778-232.
Nguyen
,
T.
,
White
,
L.
,
Vaghetto
,
R.
, and
Hassan
,
Y.
, 2019
, “
High-Fidelity Velocity Measurements in a Totally Blocked Interior Subchannel of a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
,” Nucl. Eng. Des.
,
353
, p. 110234
.10.1016/j.nucengdes.2019.11023433.
Chai
,
X.
,
Liu
,
X.
,
Xiong
,
J.
, and
Cheng
,
X.
, 2019
, “
CFD Analysis of Flow Blockage Phenomena in a LBE-Cooled 19-Pin Wire-Wrapped Rod Bundle
,” Nucl. Eng. Des.
,
344
, pp. 107
–121
.10.1016/j.nucengdes.2019.01.01934.
Marinari
,
R.
,
Di Piazza
,
I.
,
Tarantino
,
M.
, and
Forgione
,
N.
, 2019
, “
Blockage Fuel Pin Simulator Experiments and Simulation
,” Nucl. Eng. Des.
,
353
, p. 110215
.10.1016/j.nucengdes.2019.11021535.
Chai
,
X.
,
Zhao
,
L.
,
Hu
,
W.
,
Yang
,
Y.
,
Liu
,
X.
,
Xiong
,
J.
, and
Cheng
,
X.
, 2020
, “
Numerical Investigation of Flow Blockage Accident in SFR Fuel Assembly
,” Nucl. Eng. Des.
,
359
, p. 110437
.10.1016/j.nucengdes.2019.11043736.
Sarkar
,
M.
,
Velusamy
,
K.
,
Munshi
,
P.
, and
Singh
,
O. P.
, 2020
, “
Analysis of Flow and Heat Transfer Through a Partially Blocked Fuel Subassembly of Fast Breeder Reactor
,” Prog. Nucl. Energy
,
118
, p. 103142
.10.1016/j.pnucene.2019.10314237.
Goth
,
N. E.
, 2017
, “
Design and PIV Measurements on a Wire-Wrapped 61-Rod Hexagonal Fuel Assembly Experimental Facility
,” M.S. thesis,
Texas A&M University
, College Station, TX
.38.
Nguyen
,
T.
,
Goth
,
N.
,
Jones
,
P.
,
Lee
,
S.
,
Vaghetto
,
R.
, and
Hassan
,
Y.
, 2017
, “
PIV Measurements of Turbulent Flows in a 61-Pin Wire-Wrapped Hexagonal Fuel Bundle
,” Int. J. Heat Fluid Flow
,
65
, pp. 47
–59
.10.1016/j.ijheatfluidflow.2017.03.00739.
Nguyen
,
T.
,
Goth
,
N.
,
Jones
,
P.
,
Vaghetto
,
R.
, and
Hassan
,
Y.
, 2018
, “
Stereoscopic PIV Measurements of Near-Wall Flow in a Tightly Packed Rod Bundle With Wire Spacers
,” Exp. Therm. Fluid Sci.
,
92
, pp. 420
–435
.10.1016/j.expthermflusci.2017.11.00940.
Goth
,
N.
,
Jones
,
P.
,
Nguyen
,
T. D.
,
Vaghetto
,
R.
,
Hassan
,
Y.
,
Salpeter
,
N.
, and
Merzari
,
E.
, 2018
, “
PTV/PIV Measurements of Turbulent Flows in Interior Subchannels of a 61-Pin Wire-Wrapped Hexagonal Fuel Bundle
,” Int. J. Heat Fluid Flow
,
71
, pp. 295
–304
.10.1016/j.ijheatfluidflow.2018.03.02141.
Vaghetto
,
R.
,
Jones
,
P.
,
Goth
,
N.
,
Childs
,
M.
,
Lee
,
S.
,
Thien Nguyen
,
D.
, and
Hassan
,
Y. A.
, 2018
, “
Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle
,” ASME J. Fluids Eng.
,
140
(3
), p. 03114
.10.1115/1.403808642.
Baxi
,
C. B.
, and
Dalle Donne
,
M.
, 1981
, “
Helium Cooled Systems. The Gas-Cooled Fast Breeder Reactor
,” Heat Transfer and Fluid Flow in Nuclear Systems
,
Pergamon Press Inc.
, New York
, pp. 407
–462
.43.
Kirillov
,
P.
,
Bobkov
,
V.
,
Zhukov
,
A.
, and
Yuriev
,
Y.
, 2010
, “
Handbook on Thermohydraulic Calculations in Nuclear Engineering
,” Thermohydraulic Processes in Nuclear Power Facilities
, Vol.
1
, Energoatomizdat
, Moscow, Russia
.44.
Chen
,
S.
,
Chen
,
Y.
, and
Todreas
,
N.
, 2018
, “
The Upgraded Cheng and Todreas Correlation for Pressure Drop in Hexagonal Wire-Wrapped Rod Bundles
,” Nucl. Eng. Des.
,
335
, pp. 356
–373
.10.1016/j.nucengdes.2018.05.01045.
Sierra Instruments
, 2019
, “
InnovaMass 240i/241i iSeries Technical Datasheet. Version iMass8
,” accessed Aug. 24, 2020, https://www.sierrainstruments.com/userfiles/file/datasheets/technical/240i-241i-innova-mass-datasheet.pdf?x=149546.
47.
Andrade
,
E. D C.
, 1934
, “
LVIII. A Theory of the Viscosity of Liquids–Part II
,” Lond Edin Dublin Philos Mag J. Sci.
,
17
(113
), pp. 698
–732
.10.1080/1478644340946242748.
Dymond
,
J. H.
, and
Malhotra
,
R.
, 1988
, “
The Tait Equation: 100 Years On
,” Int. J. Thermophys.
,
9
(6
), pp. 941
–951
.10.1007/BF0113326249.
Noushin
,
A.
, and Hassan
,
Y. A.
, 2012
, “An Investigation of Matched Index of Refraction Technique and its Application in Optical Measurements of Fluid Flow
,” Exp. Fluids
, 53
, pp. 2011
–2020
.https://doi.org/10.1007/s00348-012-1398-x50.
Omega Engineering
, 2010
, “User's Guide: FPT-6100, FPT-6200 and FPT-6300 High Accuracy Pitot Tubes
,”
Omega Engineering
.51.
Darcy
,
H. P. G.
, 1856
, “Les Fontaines publiques de la ville de Dijon. Exposition et application des principes à suivre et des formules à employer dans les questions de distribution d'eau, etc.
,” V. Dalamont
, Paris, France
.52.
Darcy
,
H. P. G.
, 1857
, Recherches Expérimentales Relatives au Mouvement de L'eau Dans Les Tuyaux
, vol.
1
,
Mallet-Bachelier
, Paris, France
.53.
Brown
,
G. O.
, 2003
, “
The History of the Darcy-Weisbach Equation for Pipe Flow Resistance
,” Environ. Water Resour. History Am. Soc. Civ. Eng.
, 38
, pp. 34
–43
.Copyright © 2020 by ASME
You do not currently have access to this content.
