References
- Z. KAROUTAS, C. GU, and B. SHOLIN, “3-D Flow Analyses for Design of Nuclear Fuel Spacer,” Proc. 7th Int. Mtg. Nuclear Reactor Thermal-Hydraulics NURETH-7, New York, p. 3153 (1995).
- T. KRAUSS and L. MEYER, “Characteristics of Turbulent Velocity and Temperature in a Wall Channel of a Heated Rod Bundle,” Exp. Therm. Fluid Sci., 12, 75 (1996); https://doi.org/10.1016/0894-1777(95)00076-3.
- S. K. YANG and M. K. CHUNG, “Spacer Grid Effects on Turbulent Flow in Rod Bundles,” J. Korean Nucl. Sci., 28, 56 (1996).
- W. K. IN, D. S. OH, and T. H. CHUN, “CFD Analysis of Turbulent Flow in Nuclear Fuel Bundle with Flow Mixing Device,” KAERI Report TR-1296/99, p. 54, Korea Atomic Energy Research Institute (1999); https://doi.org/.
- W. K. IN, D. S. OH, and T. H. CHUN, “Flow Analysis for Optimum Design of Mixing Vane in a PWR Fuel Assembly,” J. Korean Nucl. Soc., 33, 327 (2001).
- X. Z. CUI and K. Y. KIM, “Three Dimensional Analysis of Turbulent Heat Transfer and Flow Through Mixing Vane in a Sub-Channel of Nuclear Reactor,” J. Korean Nucl. Soc., 40, 719 (2003).
- M. V. HOLLOWAY et al., “The Effect of Support Grid Features on Local, Single-Phase Heat Transfer Measurements in Rod Bundles,” J. Heat Transf., 126, 43 (2004); https://doi.org/10.1115/1.1643091.
- K. Y. KIM and J. W. SEO, “Design Optimization of Mixing Vane in Nuclear Fuel Assembly,” Proc. 6th Int. conf. Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-6), Nara, Japan, October 4–8, 2004, paper ID N6P154 (2004).
- Y. MIZUTANI et al., “Two-Phase Flow Patterns in a Four by Four Rod Bundle,” J. Nucl. Sci. Technol., 44, 6, 894 (2007); https://doi.org/10.1080/18811248.2007.9711327.
- Z. ZHANG et al., “Motion of Small Bubbles near a Grid Spacer in a Two by Three Rod Bundle,” J. Fluid Sci. Technol., 3, 1, 172 (2008); https://doi.org/10.1299/jfst.3.172.
- M. A. NAVARRO and A. A. C. SANTOS, “Numerical Evaluation of Flow Through 5 × 5 Rod Bundle: Effect of the Vane Arrangement in a Spacer Grid,” Proc. Int. Nuclear Atlantic Conf.—INAC 2009, Rio de Janeiro, Brazil, September 27–October 2, 2009 (2009).
- C. C. LIU and Y. M. FERNG, “Numerically Simulating the Thermal-Hydraulic Characteristics Within the Fuel Rod Bundle Using CFD Methodology,” Nucl. Eng. Des., 240, 3078 (2010); https://doi.org/10.1016/j.nucengdes.2010.05.021.
- M. A. NAVARRO and A. A. C. SANTOS, “Evaluation of a Numeric Procedure for Flow Simulation of a 5 × 5 PWR Rod Bundle with a Mixing Vane Spacer,” Prog. Nucl. Energy, 53, 1190 (2011); https://doi.org/10.1016/j.pnucene.2011.08.002.
- S. PARANJAPE et al., “Flow Regime Identification Under Adiabatic Upward Two-Phase Flow in a Vertical Rod Bundle Geometry,” J. Fluids Eng., 133, 091302 (2011); https://doi.org/10.1115/1.4004836.
- K. M. KRALL and E. M. SPARROW, “Turbulent Heat Transfer in the Separated, Reattached and Redevelopment Regions of a Circular Tube,” J. Heat Transf., 88, 131 (Jan. 1966); https://doi.org/10.1115/1.3691456.
- K. K. KORAM and E. M. SPARROW, “Turbulent Heat Transfer Downstream from an Unsymmetric Blockage in a Tube,” J. Heat Transf., 100, 588 (1978); https://doi.org/10.1115/1.3450861.
- M. A. HASSAN and K. REHME, “Heat Transfer near Spacer Grids in Gas-Cooled Rod Bundles,” Nucl. Technol., 52, 410 (1981); https://doi.org/10.13182/NT81-A32714.
- S. C. YAO, L. E. HOCHREITER, and W. J. LEECH, “Heat-Transfer Augmentation in Rod Bundles near Grid Spacers,” J. Heat Transf., 104, 1, 76 (1982); https://doi.org/10.1115/1.3245071.
- S. K. WANG et al., “3D Turbulence Structure and Phase Distribution Measurements in Bubbly Two-Phase Flows,” Int. J. Multiphase Flow, 13, 327 (1987); https://doi.org/10.1016/0301-9322(87)90052-8.
- U. BIEDER, F. FALK, and G. FAUCHET, “LES Analysis of the Flow in a Simplified PWR Assembly with Mixing Grid,” Prog. Nucl. Energy, 75, 15 (2014); https://doi.org/10.1016/j.pnucene.2014.03.014.
- W. E. DOMINGUEZ-ONTIVEROS and Y. A. HASSAN, “Non-Intrusive Experimental Investigation of Flow Behavior Inside a 5 × 5 Rod Bundle with Spacer Grids Using PIV and MIR,” Nucl. Eng. Des., 239, 888 (2009); https://doi.org/10.1016/j.nucengdes.2009.01.009.
- H. L. McCLUSKY et al., “Mapping of Lateral Flow Field in Typical Subchannels of a Support Grid with Vanes,” J. Fluids Eng., 125, 987 (2003); https://doi.org/10.1115/1.1625688.
- C. HERER, “3D Flow Measurements in Nuclear Fuel Rod Bundles Using Laser Doppler Velocimetry,” Proc. Fluid Measurement and Instrumentation Forum, ASME FED, Vol. 108, p. 95 (1991).
- Y. F. SHEN, Z. D. CAO, and Q. G. LU, “An Investigation of Crossflow Mixing Effect Caused by Grid Spacer with Mixing Blades in a Rod Bundle,” Nucl. Eng. Des., 125, 111 (1991); https://doi.org/10.1016/0029-5493(91)90071-O.
- K. PODILA et al., “A CFD Simulation of 5 × 5 Rod Bundle with Split-Type Spacers,” Prog. Nucl. Energy, 70, 167 (2014); https://doi.org/10.1016/j.pnucene.2013.08.012.
- X. CHENG, B. KUANG, and Y. H. YANG, “Numerical Analysis of Heat Transfer in Supercritical Water Cooled Flow Channels,” Nucl. Eng. Des., 237, 240 (2007); https://doi.org/10.1016/j.nucengdes.2006.06.011.
- X. LI, D. CHEN, and L. HU, “Numerical Investigation on Mixing Performance in Rod Bundle with Spacer Grid Based on Anisotropic Turbulent Mixing Model,” Int. J. Heat Mass Transfer, 130, 843 (2019); https://doi.org/10.1016/j.ijheatmasstransfer.2018.10.121.
- S. J. BYUN et al., “Experimental Study on the Heat Transfer Enhancement in Sub-Channels of 6 × 6 Rod Bundle with Large Scale Vortex Flow Mixing Vanes,” Nucl. Eng. Des., 339, 105 (2018); https://doi.org/10.1016/j.nucengdes.2018.09.004.
- R. K. SINHA and A. KAKODKAR, “Design and Development of the AHWR—The Indian Thorium Fuelled Innovative Nuclear Reactor,” Nucl. Eng. Des., 236, 683 (2006); https://doi.org/10.1016/j.nucengdes.2005.09.026.
- J. XIONG et al., “CFD Simulation of Swirling Flow Induced by Twist Vanes in a Rod Bundle,” Nucl. Eng. Des., 338, 52 (2018); https://doi.org/10.1016/j.nucengdes.2018.08.003.
- K. T. KIM and J. M. SUH, “Impact of Nuclear Fuel Assembly Design on Grid-to-Rod Fretting Wear,” J. Nucl. Sci. Technol., 46, 2, 149 (2009); https://doi.org/10.1080/18811248.2007.9711516.
- K. IKEDA, “CFD Application to Advanced Design for High Efficiency Spacer Grid,” Nucl. Eng. Des., 279, 73 (2014); https://doi.org/10.1016/j.nucengdes.2014.02.013.
- D. CHANG and S. TAVOULARIS, “Hybrid Simulations of the near Field of a Split-Vane Spacer Grid in a Rod Bundle,” Int. J. Heat Fluid Flow, 51, 151 (2015); https://doi.org/10.1016/j.ijheatfluidflow.2014.07.005.
- D. CHEN et al., “Thermal–Hydraulic Performance of a 5 × 5 Rod Bundle with Spacer Grid in a Nuclear Reactor,” Appl. Therm. Eng., 103, 1416 (2016); https://doi.org/10.1016/j.applthermaleng.2016.05.028.
- D. J. MILLER, F. B. CHEUNG, and S. M. BAJOREK, “On the Development of a Grid-Enhanced Single-Phase Convective Heat Transfer Correlation,” Nucl. Eng. Des., 264, Suppl. C, 56 (2013); https://doi.org/10.1016/j.nucengdes.2012.11.023.
- A. TANASE and D. C. GROENEVELD, “An Experimental Investigation on the Effects of Flow Obstacles on Single Phase Heat Transfer,” Nucl. Eng. Des., 288, Suppl. C, 195 (2015); https://doi.org/10.1016/j.nucengdes.2015.04.004.
- Y. XIAO, J. PAN, and H. GU, “Numerical Investigation of Spacer Effects on Heat Transfer of Supercritical Fluid Flow in an Annular Channel,” Int. J. Heat Mass Transfer, 121, 343 (2018); https://doi.org/10.1016/j.ijheatmasstransfer.2018.01.030.
- Q.-Y. REN et al., “Phase Distribution Characteristics of Bubbly Flow in 5 × 5 Vertical Rod Bundles with Mixing Vane Spacer Grids,” Exp. Therm. Fluid Sci., 96, 451 (2018); https://doi.org/10.1016/j.expthermflusci.2018.04.002.
- S. HOSOKAWA, K. HAYASHI, and A. TOMIYAMA, “Void Distribution and Bubble Motion in Bubbly Flows in a 4 × 4 Rod Bundle. Part I: Experiments,” J. Nucl. Sci. Technol., 51, 220 (2014); https://doi.org/10.1080/00223131.2013.862189.
- X. YANG et al., “Experimental Study of Interfacial Area Transport in Air-Water Two Phase Flow in a Scaled 8 × 8 BWR Rod Bundle,” Int. J. Multiphase Flow, 50, 16 (2013); https://doi.org/10.1016/j.ijmultiphaseflow.2012.10.006.
- B. J. YUN et al., “Flow Structure of Subcooled Boiling Water Flow in a Subchannel of 3 × 3 Rod Bundles,” J. Nucl. Sci. Technol., 45, 402 (2008); https://doi.org/10.1080/18811248.2008.9711450.
- S. PARANJAPE, M. ISHII, and T. HIBIKI, “Modeling and Measurement of Interfacial Area Concentration in Two-Phase Flow,” Nucl. Eng. Des., 240, 2329 (2010); https://doi.org/10.1016/j.nucengdes.2009.11.009.
- T. ARAI et al., “Development of a Subchannel Void Sensor and Two-Phase Flow Measurement in 10 × 10 Rod Bundle,” Int. J. Multiphase Flow, 47, 183 (2012); https://doi.org/10.1016/j.ijmultiphaseflow.2012.07.012.
- D. K. CHANDRAKER, A. K. NAYAK, and P. K. VIJAYAN, “Effect of Spacer on the Dryout of BWR Fuel Rod Assemblies,” Nucl. Eng. Des., 294, 262 (2015); https://doi.org/10.1016/j.nucengdes.2015.09.004.
- K. MISHIMA and M. ISHII, “Flow Regime Transition Criteria for Upward Two-Phase Flow in Vertical Tubes,” Int. J. Heat Mass Transfer, 27, 5, 723 (1984); https://doi.org/10.1016/0017-9310(84)90142-X.
- J. E. JULIA et al., “Axial Development of Flow Regime in Adiabatic Upward Two-Phase Flow in a Vertical Annulus,” Trans. ASME, J. Fluids Eng., 131, 021302-1-11 (Feb. 2009); https://doi.org/10.1115/1.3059701.
- M. KUMAR et al., “CFD Simulation of Boiling Flows Inside Fuel Rod Bundle of a Natural Circulation BWR During SBO,” Nucl. Eng. Des., 338, 300 (2018); https://doi.org/10.1016/j.nucengdes.2018.08.011.
- R. GOPINATH, N. BASU, and V. K. DHIR, “Interfacial Heat Transfer During Subcooled Flow Boiling,” Int. J. Heat Mass Transfer, 45, 3947 (2002); https://doi.org/10.1016/S0017-9310(02)00102-3.
- V. PRODANOVIC, D. FRASER, and M. SALCUDEAN, “Bubble Behavior in Subcooled Flow Boiling of Water at Low Pressures and Low Flow Rates,” Int. J. Multiphase Flow, 28, 1 (2002); https://doi.org/10.1016/S0301-9322(01)00058-1.
- J. Y. TU and G. H. YEOH, “On Numerical Modeling of Low Pressure Subcooled Boiling Flows,” Int. J. Heat Mass Transfer, 45, 1197 (2002); https://doi.org/10.1016/S0017-9310(01)00230-7.
- J. FANG et al., “Interface-Resolved Simulations of Reactor Flows,” Nucl. Technol., 206, 133 (2020); https://doi.org/10.1080/00295450.2019.1620056.
- J. FANG et al., “Direct Numerical Simulation of Reactor Two-Phase Flows Enabled by High Performance Computing,” Nucl. Eng. Des., 330, 409 (2018); https://doi.org/10.1016/j.nucengdes.2018.02.024.
- A. M. THOMAS et al., “Estimation of Shear-Induced Lift Force in Laminar and Turbulent Flows,” Nucl. Technol., 190, 3, 274 (2015); https://doi.org/10.13182/NT14-72.
- J. FANG, M. RASQUIN, and I. A. BOLOTNOV, “Interface Tracking Simulations of Bubbly Flows in PWR Relevant Geometries,” Nucl. Eng. Des., 312, Suppl. C, 205 (2017); https://doi.org/10.1016/j.nucengdes.2016.07.002.
- M. D. ZIMMER and I. A. BOLOTNOV, “Slug-to-Churn Vertical Two-Phase Flow Regime Transition Study Using an Interface Tracking Approach,” Int. J. Multiphase Flow, 115, 196 (2019); https://doi.org/10.1016/j.ijmultiphaseflow.2019.04.003.
- M. LI et al., “Development of a New Contact Angle Control Algorithm for Level-Set Method,” J. Fluids Eng., 141, 6, 61301 (2018); https://doi.org/10.1115/1.4041987.
- M. LI and I. A. BOLOTNOV, “Interface Tracking Simulation of Phase-Change Phenomena: Boiling and Condensation Verification,” Proc. ASME 2016 Fluids Engineering Division Summer Mtg./ASME 2016 Heat Transfer Summer Conf./ASME 2016 14th Int. Conf. Nanochannels, Microchannels, and Minichannels, Washington, District of Columbia, July 10–14, 2016, p. V01AT06A001, American Society of Mechanical Engineers (2016).
- M. LI and I. A. BOLOTNOV, “Development of Evaporation and Condensation Model—Pool Boiling Simulation Using ITM Approach,” Trans. Am. Nucl. Soc., 118, 1038 (2018).
- J. FANG et al., “Interface Tracking Investigation of Geometric Effects on the Bubbly Flow in PWR Subchannels,” Nucl. Sci. Eng., 193, 1–2, 46 (2018); https://doi.org/10.1080/00295639.2018.1499280.
- J. FANG and I. A. BOLOTNOV, “Bubble Tracking Analysis of PWR Two-Phase Flow Simulations Based on the Level Set Method,” Nucl. Eng. Des., 323, Suppl. C, 68 (2017); https://doi.org/10.1016/j.nucengdes.2017.07.034.
- J. FANG and I. A. BOLOTNOV, “Bubble Tracking Simulations of Turbulent Two-Phase Flows”, Proc. ASME 2016 Fluids Engineering Division Summer Mtg., Washington, District of Columbia, July 10–14, 2016, FEDSM2016-1005 (2016).
- S. ELGHOBASHI, “Direct Numerical Simulation of Turbulent Flows Laden with Droplets or Bubbles,” Ann. Rev. Fluid Mech., 51, 1, 217 (2019); https://doi.org/10.1146/annurev-fluid-010518-040401.
- A. D. U. CLUZEAU, G. BOIS, and A. TOUTANT, “Analysis and Modelling of Reynolds Stresses in Turbulent Bubbly Up-Flows from Direct Numerical Simulations,” J. Fluid Mech., 866, 132 (2019); https://doi.org/10.1017/jfm.2019.100.
- G. BOIS, “Direct Numerical Simulation of a Turbulent Bubbly Flow in a Vertical Channel: Towards an Improved Second-Order Reynolds Stress Model,” Nucl. Eng. Des., 321, 92 (2017); https://doi.org/10.1016/j.nucengdes.2017.01.023.
- A. SERIZAWA, I. KATAOKA, and I. MICHIYOSHI, “Turbulent Structure of Air-Water Bubbly Flow—III. Transport Properties,” Int. J. Multiphase Flow, 2, 247 (1975); https://doi.org/10.1016/0301-9322(75)90013-0.
- M. YAO, M. NAKATANI, and K. SUZUKI, “Flow Visualization and Heat Transfer Experiments in a Turbulent Channel Flow Obstructed with an Inserted Square Rod,” Int. J. Heat Fluid Flow, 16, 389 (1995); https://doi.org/10.1016/0142-727X(95)00047-T.
- S. DOERFFER, D. C. GROENEVELD, and J. R. SCHENK, “Experimental Study of the Effects of Flow Inserts on Heat Transfer and Critical Heat Flux,” Proc. 4th Int. Conf. Nuclear Engineering, New Orleans, Louisiana, March 10–14, 1996, Vol. 1, p. 41, Part A (1996).
- A. A. TROSHKO and Y. A. HASSAN, “A Two-Equation Turbulent Model of Turbulent Bubbly Flows,” Int. J. Multiphase Flow, 27, 1965 (2001); https://doi.org/10.1016/S0301-9322(01)00043-X.
- I. L. PIORO et al., “Effects of Flow Obstacles on the Critical Heat Flux in a Vertical Tube Cooled with Upward Flow of R-134a,” Int. J. Heat Mass Transfer, 45, 4417 (2002); https://doi.org/10.1016/S0017-9310(02)00150-3.
- T. H. LEE, G. C. PARK, and D. J. LEE, “Local Flow Characteristics of Subcooled Boiling Flow of Water in a Vertical Concentric Annulus,” Int. J. Multiphase Flow, 28, 1351 (2002); https://doi.org/10.1016/S0301-9322(02)00026-5.
- J. Y. TU and G. H. YEOH, “Development of a Numerical Model for Subcooled Boiling Flow,” Proc. 3rd Int. Conf. CFD in the Minerals and Process Industries CSIRO, Melbourne, Australia, December 10–12, 2003 (2003).
- E. KREPPER, D. LUCAS, and H. M. PRASSER, “On the Modeling of Bubbly Flow in Vertical Pipes,” Nucl. Eng. Des., 235, 597 (2005); https://doi.org/10.1016/j.nucengdes.2004.09.006.
- G. H. YEOH and J. Y. TU, “A Unified Model Considering Force Balances for Departing Vapour Bubbles and Population Balance in Subcooled Boiling Flow,” Nucl. Eng. Des., 235, 1251 (2005); https://doi.org/10.1016/j.nucengdes.2005.02.015.
- E. KREPPER et al., “Experimental and Numerical Studies of Void Fraction Distribution in Rectangular Bubble Columns,” Nucl. Eng. Des., 237, 4, 399 (2007); https://doi.org/10.1016/j.nucengdes.2006.07.009.
- D. LUCAS, E. KREPPER, and H.-M. PRASSER, “Use of Models for Lift, Wall and Turbulent Dispersion Forces Acting on Bubbles for Poly-Disperse Flows,” Chem. Eng. Sci., 62, 15, 4146 (2007); https://doi.org/10.1016/j.ces.2007.04.035.
- V. USTINENKO et al., “Validation of CFD-BWR, a New Two-Phase Computational Fluid Dynamics Model for Boiling Water Reactor Analysis,” Nucl. Eng. Des., 238, 660 (2008); https://doi.org/10.1016/j.nucengdes.2007.02.046.
- Z. ZHANG et al., “Numerical Simulation of Bubble Motion About a Grid Spacer in a Rod Bundle,” J. Power Energy Syst., 3, 393 (2009); https://doi.org/10.1299/jpes.3.393.
- C. R. ZHAO and P. X. JIANG, “Experimental Study of In-Tube Cooling Heat Transfer and Pressure Drop Characteristics of R134a at Supercritical Pressures,” Exp. Therm. Fluid Sci., 35, 1293 (2011); https://doi.org/10.1016/j.expthermflusci.2011.04.017.
- X. YANG et al., “Measurement and Modeling of Two Phase Flow Parameters in Scaled 8 × 8 BWR Rod Bundle,” Int. J. Heat Fluid Flow, 34, 85 (2012); https://doi.org/10.1016/j.ijheatfluidflow.2012.02.001.
- X. ZHU, S. MOROOKA, and Y. OKA, “Numerical Investigation of Grid Spacer Effect on Heat Transfer of Supercritical Water Flows in a Tight Rod Bundle,” Int. J. Therm. Sci., 76, 245 (2014); https://doi.org/10.1016/j.ijthermalsci.2013.10.003.
- X. LI and Y. GAO, “Methods of Simulating Large-Scale Rod Bundle and Application to a 17 × 17 Fuel Assembly with Mixing Vane Spacer Grid,” Nucl. Eng. Des., 267, 10 (2014); https://doi.org/10.1016/j.nucengdes.2013.11.064.
- K. GOODHEART et al., “CFD Validation of Void Distribution in a Rod Bundle with Spacer,” Proc. 22nd Int. Conf. Nuclear Engineering (ICONE22), Prague, Czech Republic, July 7–11, 2014 (2014).
- A. KAWAHARA et al., “Effects of Grid Spacer with Mixing Vane on Entrainments and Depositions in Two-Phase Annular Flows,” Nucl. Eng. Technol., 47, 389 (2015); https://doi.org/10.1016/j.net.2015.04.002.
- M. ZIMMERMANN et al., “Numerical Investigation and Modeling of Two-Phase Flow Sweeping in Rod Bundles with Mixing Vane Grid Spacers,” Ann. Nucl. Energy, 85, 403 (2015); https://doi.org/10.1016/j.anucene.2015.04.040.
- A. KAWAHARA et al., “Hydrodynamic Effects of Mixing Vane Attached to Grid Spacer on Two-Phase Annular Flows,” Nucl. Eng. Des., 310, 648 (2016); https://doi.org/10.1016/j.nucengdes.2016.10.036.
- C. Y. LEE, W. K. IN, and J. K. LEE, “Augmentation of Single-Phase Forced Convection Heat Transfer in Tightly Arrayed Rod Bundle with Twist-Vane Spacer Grid,” Exp. Therm. Fluid Sci., 76, 185 (2016); https://doi.org/10.1016/j.expthermflusci.2016.03.006.
- H. MAO et al., “Modeling of Spacer Grid Mixing Effects Through Mixing Vane Crossflow Model in Subchannel Analysis,” Nucl. Eng. Des., 320, 141 (2017); https://doi.org/10.1016/j.nucengdes.2017.05.003.
- S. CHENG, H. CHEN, and X. ZHANG, “CFD Analysis of Flow Field in a 5 × 5 Rod Bundle with Multi-Grid,” Ann. Nucl. Energy, 99, 464 (2017); https://doi.org/10.1016/j.anucene.2016.09.053.
- A. B. MASKAL and F. AYDOGAN, “Mathematical Spacer Grid Models for Single Phase Flow,” Ann. Nucl. Energy, 103, 130 (2017); https://doi.org/10.1016/j.anucene.2017.01.019.
- A. B. MASKAL and F. AYDOGAN, “Mathematical Spacer Grid Models for Two Phase Flow,” Ann. Nucl. Energy, 103, 173 (2017); https://doi.org/10.1016/j.anucene.2017.01.024.
- B. KONCAR and S. KOSMRLJ, “Simulation of Turbulent Flow in MATIS-H Rod Bundle with Split-Type Mixing Vanes,” Nucl. Eng. Des., 327, 112 (2018); https://doi.org/10.1016/j.nucengdes.2017.12.017.
- T. CONG and X. ZHANG, “Numerical Study of Bubble Coalescence and Breakup in the Reactor Fuel Channel with a Vaned Grid,” Energies, 11, 256 (2018); https://doi.org/10.3390/en11010256.
- K. PODILA and Y. F. RAO, “CFD Simulation of Heated Tight-Lattice Rod Bundles for an IAEA Benchmark,” Prog. Nucl. Energy, 108, 222 (2018); https://doi.org/10.1016/j.pnucene.2018.06.001.
- D. LIU and H. GU, “Study on Heat Transfer Behavior in Rod Bundles with Spacer Grid,” Int. J. Heat Mass Transfer, 120, 1065 (2018); https://doi.org/10.1016/j.ijheatmasstransfer.2017.12.121.
- M. A. VOROBYEV and O. N. KASHINSKY, “Heat Transfer of a Bubbly Flow in a Vertical Rod Bundle 3 × 3,” IOP Conf. Ser. J. Phys. Conf. Ser., 1105, 012073 (2018); https://doi.org/10.1088/1742-6596/1105/1/012073.
- Y. WANG, Y. M. FERNG, and L. X. SUN, “CFD Assist in Design of Spacer-Grid with Mixing-Vane for a Rod Bundle,” Appl. Therm. Eng., 149, 565 (2019); https://doi.org/10.1016/j.applthermaleng.2018.12.090.