Publications

Journal Papers

Published:

Liu, Q., Kelly, J., and Sun, X., April 2021, “Study on Interfacial Friction in the Inverted Annular Film Boiling Regime,” Nuclear Engineering and Design, 375, 111082 (9 pp).

Liu, Q., Kelly, J., and Sun, X., March 2021, “Flow Regime Transition in the Post-CHF Flow Regimes under Subcooled and Low-quality Conditions,” International Journal of Multiphase Flow, 136, 103543 (9 pp).

Wang, C., Liu, Y., Sun, X., and Sabharwall, P., February 2021, “A Hybrid Porous Model for Full Reactor Core Scale CFD Investigation of a Prismatic HTGR,” Annals of Nuclear Energy, 151, 107916 (15 pp).

Liu, Q., Sun, H., Liu, Y. Kelly, J., and Sun, X., February 2021, “Experimental Study of Post-CHF Heat Transfer in a Vertical Tubular Test Section,” International Journal of Heat and Mass Transfer, 166, 120697 (13 pp).

Zhang, S. and Sun, X., November 2020, “Convective and Radiative Heat Transfer in Molten Salts,” Nuclear Technology, 206(11), pp. 1721-1739.

Liu, Y., Wang, C., Qian, Y., Sun, X., and Liu, Y., August 2020, “Uncertainty Analysis of PIV Measurements in Bubbly Flows Considering Sampling and Bubble Effects with Ray Optics Modeling,” Nuclear Engineering and Design, 364, 110677 (14 pp).

Liu, Q. and Sun, X., July 2020, “Wall Heat Transfer in the Inverted Annular Film Boiling Regime,” Nuclear Engineering and Design, 363, 110660 (11 pp).

Zhang, S., Sun, X., and Dominguez-Ontiveros, E.E., July 2020, “Numerical Study on Convective Heat Transfer and Friction Characteristics of Molten Salts in Circular Tubes,” Annals of Nuclear Energy, 142, 107375 (15 pp).

Wang, C., Sun, X., and Sabharwall, P., June 2020, “CFD Investigation of MHTGR Natural Circulation and Decay Heat Removal in P-LOFC Accident,” Frontier in Energy Research, 8, Article 129.

Shi, S., Wang, D., Qian, Y., Sun, X., Liu, Y., and Tentner, A., June 2020, “Liquid-phase Turbulence Measurements in Air-water Two-phase Flows Using Particle Image Velocimetry,” Progress in Nuclear Energy, 124, 103334 (14 pp).

Wu, X., Liu, Y., Kearfott, K., and Sun, X., March 2020, “Evaluation of Public Dose from FHR Tritium Release with Consideration of Meteorological Uncertainties,” Science of the Total Environment, 709, 136085 (13 pp).

Liu, Y., Sun, X., and Dinh, N.T., December 2019, “Validation and Uncertainty Quantification of Multiphase-CFD Solvers: A Data-driven Bayesian Framework Supported by High-resolution Experiments,” Nuclear Engineering and Design, Special Issue on Trends and Perspectives in Nuclear Thermal-Hydraulics, 354, Paper ID: 110200 (19 pp).

Liu, Y., Dinh, N.T., Smith, R.C., and Sun, X., August 2019, “Uncertainty Quantification of Two-Phase Flow and Boiling Heat Transfer Simulations through a Data-Driven Modular Bayesian Approach,” International Journal of Heat and Mass Transfer, 138, pp. 1096-1116.

Wang, C., Sun, X., and Christensen, R.N., September 2019, “Multiphysics Simulation of Moisture-Graphite Oxidation in MHTGR,” Annals of Nuclear Energy, 131, pp. 483-495.

Chen, M., Sun, X., and Christensen, R.N., March 2019, “Thermal-hydraulics Performance of Printed Circuit Heat Exchangers with Zigzag Flow Channels,” International Journal Heat and Mass Transfer, 130, pp. 356-367.

Lin, H.C., Zhang, S., Diamond, D., Bajorek, S., Christensen, R., Guo, Y., Yoder, G., Shi, S., Lv, Q., and Sun, X., February 2019, “Phenomena Identification and Ranking Table Study for Thermal Hydraulics for Advanced High Temperature Reactor,” Annals of Nuclear Energy, 124, pp. 257-269.

Zhang, S., Wu, X., Shi, S., Sun, X., Christensen, R., and Yoder, G., December 2018, “A Coupled Heat Transfer and Tritium Mass Transport Model for a Double-Wall Heat Exchanger Design for FHRs,” Annals of Nuclear Energy, 122, pp. 328-339.

Liu, Q., Shi, S., Sun, X., and Kelly, J., December 2018, “Thermal Hydraulic Performance Analysis of a Post-CHF Heat Transfer Test Facility,” Nuclear Engineering and Design, 339, pp. 53-64.

Rahnema, F., Sun, X., Petrovic, B., Diamond, D., Bajorek, S., Guo, Y., Yoder, G., Zhang, D., and Burke, P., November 2018, “Phenomena Identification and Categorization by the Required Level of Multiphysics Coupling in FHR Modeling and Simulation,” Annals of Nuclear Energy, 121, pp. 540-551.

Lin, H.C., Lv, Q., Shi, S., Sun, X., Christensen, R., and Yoder, G., November 2018, “Code Validation of a Scaled-down DRACS Model in RELAP5/SCDAPSIM/MOD 4.0,” Annals of Nuclear Energy, 121, pp. 452-460.

Wu, X., Shi, S., Zhang, S., Arcilesi, D., Christensen, R., Sabharwall, P., and Sun, X., November 2018, “Mass Transport Analysis for Tritium Removal in FHRs,” Annals of Nuclear Energy, 121, pp. 250-259.

Yoon, S.-J., O’Brien, J., Sabharwall, P., Wegman, K., and Sun, X., August 2018, “Study on Effects of Heat Loss and Channel Deformation on the Thermal-hydraulic Performance of the Semicircular Straight Channel Printed Circuit Heat Exchangers,” Journal of Thermal Science and Engineering Applications, Transactions of the ASME, 10, pp. 041013-1 – 041013-14.

Chen, M., Sun, X., Christensen, R.N., Skavdahl, I., Utgikar, V., and Sabharwall, P., May 2018, “Dynamic Behavior of a High-Temperature Printed Circuit Heat Exchanger: Numerical Modeling and Experimental Investigation,” Applied Thermal Engineering, 135, pp. 246-256.

Shi, S., Zhu, Q., Sun, X., and Ishii, M., February 2018, “Assessment of RELAP5/MOD3.2 for Startup Transients in a Natural Circulation Test Facility,” Annals of Nuclear Energy, 112, pp. 257-266.

Yoon, S.-J., O’Brien, J., Chen, M., Sabharwall, P., and Sun, X., August 2017, “Development and Validation of Nusselt Number and Friction Factor Correlations for Laminar Flow in Semi-circular Zigzag Channel of Printed Circuit Heat Exchanger,” Applied Thermal Engineering, 123, pp. 1327-1344.

Lv, Q., Lin, H.C., Shi, S., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., November 2016, “Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility,” Nuclear Technology, NURETH-16 Special Issue, 196(2), pp. 319-337.

Zhou, X., Sun, X., and Y. Liu, December 2016, “Liquid-Phase Turbulence Measurements in Air-Water Two-Phase Flows over a Wide Range of Void Fractions,” Nuclear Engineering and Design, Special Issue: Proceedings of the 2015 Japan-US Seminar on Two-phase Flow Dynamics, 310, pp. 534-543.

Skavdahl, I., Utgikar, V., Christensen, R., Chen, M., Sun, X., and Sabharwall, P., December 2016, “Control of Advanced Reactor-Coupled Heat Exchanger System: Incorporation of Reactor Dynamics in System Response to Load Disturbances,” Nuclear Engineering and Technology, 48(6), pp. 1349-1359.

Chen, M., Sun, X., Christensen, R.N., Skavdahl, I., Utgikar, V., and Sabharwall, P., September 2016, “Pressure Drop and Heat Transfer Characteristics of a High-temperature Printed Circuit Heat Exchanger,” Applied Thermal Engineering, 108, pp. 1409-1417.

Chen, M., Sun, X., Christensen, R.N., Shi, S., Skavdahl, I., Utgikar, V., and Sabharwall, P., November 2016, “Experimental and Numerical Study of a Printed Circuit Heat Exchanger,” Annals of Nuclear Energy, 97, pp. 221-232.

Kim, I.H., Zhang, X., Christensen, R. and Sun, X., August 2016, “Design Study and Cost Assessment of Straight, Zigzag, S-shape, and OSF PCHEs for a FLiNaK-SCO2 Secondary Heat Exchanger in FHRs,” Annals of Nuclear Energy, 94, pp. 129-137.

Ham, T.K., Arcilesi Jr., D.J., Kim, I.H., Sun, X., Christensen, R.N., Oh, C.H., and Kim, E.S., April 2016, “Computational Fluid Dynamics Analysis of the Initial Stages of a VHTR Air-Ingress Accident using a Scaled-down Model,” Nuclear Engineering and Design, 300, pp. 517-529.

Skavdahl, I., Utgikar, V.P., Christensen, R., Sabharwall, P., Chen, M., and Sun, X., April 2016, “Modeling and Simulation of Control System Response to Temperature Disturbances in a Coupled Heat Exchangers-AHTR System,” Nuclear Engineering and Design, 300, pp. 161-172.

Mylavarapu, S.K., Sun, X., and Christensen, R.N., March 2016, “Hydrodynamically Developing and Fully-Developed Laminar Flows in a Semicircular Duct: Analytical and Computational Analyses,” Nuclear Science and Engineering, 182(3), pp. 319-331.

Sabharwall, P., O’Brien, J.E., Yoon, S.J., and Sun, X., December 2015, “Experimental Facility for Development of High-Temperature Reactor Technology: Instrumentation Needs and Challenges,” European Physical Journal (EPJ) N: Nuclear Sciences and Technologies, 1, 14.

Chen, M., Kim, I.H., Sun, X., Christensen, R., Utgikar, V., and Sabharwall, P., August 2015, “Transient Analysis of an FHR Coupled to a Helium Brayton Power Cycle,” Progress in Nuclear Energy, 83, pp. 283-293.

Arcilesi, D.J., Ham, T.K., Kim, I.H., Sun, X., Christensen, R.N., and Oh, C.H., July 2015, “Scaling and Design Analyses of a Scaled-down, High-temperature Test Facility for Experimental Investigation of the Initial Stages of a VHTR Air-ingress Accident,” Nuclear Engineering and Design, 288, pp. 141-162.

Bartel, N., Chen, M., Utgikar, V.P., Sun, X., Kim, I.-H., Christensen, R., Sabharwall, P., July 2015, “Comparative Analysis of Compact Heat Exchangers for Application as the Intermediate Heat Exchanger for Advanced Nuclear Reactors,” Annals of Nuclear Energy, 81, pp. 143-149.

Sun, W., Niu L., Chen, S., Sun, X., Hou, Y., June 2015, “Numerical Investigation of Nitrogen Spontaneous Condensation Flow in Cryogenic Nozzles using Varying Nucleation Theories,” Cryogenics, 68, pp. 19-29.

Lv, Q., Wang, X., Kim, I.H., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., April 2015, “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for FHRs,” Nuclear Engineering and Design, 285, pp. 197-206.

Lv, Q., Lin, H.C., Kim, I.H., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G.L., Wilson, D.F., and Sabharwall, P., March 2015, “DRACS Thermal Performance Evaluation for FHR,” Annals of Nuclear Energy, 77, pp. 115-128.

Doup, B., Zhou, X., Kim, I.H., and Sun, X., 2013, “Measurements of the Local Relative Velocity and the Profile Effects on Prediction of the Area-averaged Relative Velocity,” Multiphase Science and Technology, 25(2-4), pp. 169-199 (actually published in July 2014).

Wang, X. and Sun, X., Sept. 2014, “Numerical Simulations of Air-water Cap-bubbly Flows Using Two-group Interfacial Area Transport Equation,” Annals of Nuclear Energy, 71, pp. 399-410.

Kim, I. and Sun, X., April 2014, “CFD Study and PCHE Design for Secondary Heat Exchangers with FLiNaK-Helium for SmAHTR,” Nuclear Engineering and Design, 270, pp. 325-333.

Mylavarapu, S., Sun, X., Glosup, R., Christensen, R.N., and Patterson, M., April 2014, “Thermal Hydraulic Performance Testing of Printed Circuit Heat Exchangers in a High-Temperature Helium Test Facility,” Applied Thermal Engineering, 65(1-2), pp. 605-614.

Zhou, X., Doup, B., and Sun, X., Dec. 2013, “Measurements of Liquid-phase Turbulence in Gas-liquid Two-phase Flows using Particle Image Velocimetry,” Measurement Science and Technology, 24(12), 125303 (19 pp).

Doup, B., Zhou, X., and Sun, X., Oct. 2013, “Local Gas and Liquid Parameter Measurements in Air-Water Two-Phase Flows,” Nuclear Engineering and Design, 263, pp. 273-283.

Figley, J., Sun, X., Mylavarapu, S., and Hajek, B., Sept. 2013, “Numerical Study on Thermal Hydraulic Performance of a Printed Circuit Heat Exchanger,” Progress in Nuclear Energy, 68, pp. 89-96.

Wang, X., Sun, X., Doup, B., and Zhao, H., 2012, “Dynamic Modeling Strategy for Flow Regime Transition in Gas-liquid Two-phase Flows,” Journal of Computational Multiphase Flows, 4(4), pp. 387-397.

Mylavarapu, S., Sun, X., Christensen, R.N., Unocic, R.R., Glosup, R.E., and Patterson, M.W., August 2012, “Fabrication and Design Aspects of High-Temperature Compact Diffusion Bonded Heat Exchangers,” Nuclear Engineering and Design, 249, pp. 49-56.

Wang, X. and Sun, X., July 2011, “Effects of Non-uniform Inlet Boundary Conditions and Lift Force on Prediction of Phase Distribution in Upward Bubbly Flows with Fluent-IATE,” Nuclear Engineering and Design, 241(7), pp. 2500-2507.

Eades, M., Flanders, J., McMurray, N., Denning, R., Sun, X., Windl, W., and Blue, T., June/July 2011, “Space Molten Salt Reactor Concept for Nuclear Electric Propulsion and Surface Power,” Journal of the British Interplanetary Society, 64(6/7), pp. 186-193.

Wang, X., Sun, X., and Duval, W.M., June 2011, “Predictions of Phase Distribution in Liquid-Liquid Two-Component Flow,” Microgravity Science and Technology, 23(3), pp. 293-303.

Vasavada, S., Sun, X., Ishii, M., and Duval, W., May 2011, “An Experimental Study of Two-Phase Flow in Simulated Reduced-Gravity Condition: Dispersed Droplet to Slug Flow Transition and Slug Flow,” Experiments in Fluids, 50(5), pp. 1373-1384.

Wang, X. and Sun, X., Oct. 2010, “A Characteristic Analysis of One-Dimensional Two-Fluid Model with Interfacial Area Transport Equation,” Journal of Applied Mathematics, 2010, Article ID 476839, doi:10.1155/2010/476839, Open access journal.

Wang, X. and Sun, X., Nov. – Dec. 2010, “Three-dimensional Simulations of Air-water Bubbly Flows,” International Journal of Multiphase Flow, 36(11-12), pp. 882-890.

Aldemir, T., Guarro, S., Mandelli, D., Kirschenbaum, J., Mangan, L.A., Bucci, P., Yau, M., Ekici, E., Miller, D.W., Sun, X., Arndt, S.A., Oct. 2010, “Probabilistic Risk Assessment Modeling of Digital Instrumentation and Control Systems Using Two Dynamic Methodologies,” Reliability Engineering and System Safety, 95(10), pp. 1011-1039.

Ishii, M., Kim, S, Sun, X., and Hibiki, T., March 2009, “Interfacial Area Transport Equation and Implementation into Two-Fluid Model,” Journal of Thermal Science and Engineering Applications, Transactions of the ASME, 1(1), pp. 011005-1-

Mylavarapu, S., Sun, X., Figley, J., Needler, N.J., and Christensen, R.N., November 2009, “Investigation of High-Temperature Printed Circuit Heat Exchangers for VHTRs,” Journal of Engineering for Gas Turbines and Power, Transactions of the ASME, 131(6), pp. 062905-01-

Vasavada, S., Sun, X., Ishii, M., and Duval, W., April 2009, “Benchmarking of the One-Dimensional One-Group Interfacial Area Transport Equation for Reduced Gravity Bubbly Flows,” International Journal of Multiphase Flow, 35(4), pp. 323-334.

Wang, X. and Sun, X., July 2009, “CFD Simulation of Phase Distribution in Adiabatic Upward Bubbly Flows Using Interfacial Area Transport Equation,” Nuclear Technology, 167(1), pp. 71-82.

Liu, Y., Hibiki, T., Sun, X., Ishii, M., and Kelly, J.M., 2008, “Drag Coefficient in One-dimensional Two-group Two-fluid Model,” International Journal of Heat and Fluid Flow, 29(5), pp. 1402-1410.

Smith, S.E., Sun, X., Ford, A., and Fentiman, A.W., 2008, “MCNP Simulation of Neutron Energy Spectra for a TN–32 Dry Shielded Container,” Annals of Nuclear Energy, 35(7), pp. 1296-1300.

Vasavada, S., Sun, X., Ishii, M., and Duval, W., 2007, “Study of Two-phase Flows in Reduced Gravity using Ground based Experiments,” Experiments in Fluids, 43(1), pp. 53-75.

Lopez de Bertodano, M., Sun, X., Ishii, M., and Ulke, A., 2006, “Phase Distribution in the Cap Bubble Regime in a Vertical Rectangular Channel,” Journal of Fluids Engineering, Transactions of the ASME, 128(4), pp. 811-818.

Kuran, S., Xu, Y., Sun, X., Cheng, L., Yoon, H.J., Revankar, S.T., Ishii, M., and Wang, W., 2006, “Startup Transient Simulation for Natural Circulation Boiling Water Reactors in PUMA Facility,” Nuclear Engineering and Design, 236(22), pp. 2365-2375.

Ishii, M., Kuran, S., Sun, X., Cheng, L., Xu, Y., Yoon, H.J., and Revankar, S.T., 2006, “Experimental Study on Stability of Startup in Natural Circulation BWRs with and without Nuclear Coupling,” Multiphase Science and Technology, 18(4), pp. 335-358.

Ishii, M. and Sun, X., 2006, “Interfacial Characteristics of Two-phase Flow,” Multiphase Science and Technology, 18(1), pp. 1-29.

Sun, X., Vasavada, S., Choi, S.W., Kim, S., Ishii, M., and S.G. Beus, 2005, “Interfacial Structure in an Air-water Planar Bubble Jet,” Experiments in Fluids, 38(4), pp. 426-439.

Situ, R., Hibiki, T., Sun, X., Mi, Y., Ishii, M., 2004, “Axial Development of Subcooled Boiling Flow in an Internally Heated Annulus,” Experiments in Fluids, 37(4), pp. 589-603.

Situ, R., Hibiki, T., Sun, X., Mi, Y., Ishii, M., 2004, “Flow Structure of Subcooled Boiling Flow in an Internally Heated Annulus,” International Journal of Heat and Mass Transfer, 47(24), pp. 5351-5364.

Sun, X., Paranjape, S., Kim, S., H. Goda, Ishii, M., and Kelly, J.M., 2004, “Local Liquid Velocity in Vertical Air-water Downward Flow,” Journal of Fluids Engineering, Transactions of the ASME, 126(4), pp. 539-545.

Ishii, M., Paranjape, S.S., Kim, S., and Sun, X., 2004, “Interfacial Structures and Interfacial Area Transport in Downward Two-phase Bubbly Flow,” International Journal of Multiphase Flow, 30(7-8), 779-801.

Sun, X., Kuran, S., and Ishii, M., 2004, “Cap Bubbly-to-Slug Flow Regime Transition in a Vertical Annulus,” Experiments in Fluids, 37(3), pp. 458-464.

Sun, X., Kim, S., Ishii, M., and Beus, S.G., 2004, “Model Evaluation of Two-group Interfacial Area Transport Equation for Confined Upward Flow,” Nuclear Engineering and Design, 230(1-3), 27-47.

Sun, X., Kim, S., Ishii, M., and Beus, S.G., 2004, “Modeling of Bubble Coalescence and Disintegration in Confined Upward Two-phase Flow,” Nuclear Engineering and Design, 230(1-3), 3-26.

Sun, X., Paranjape, S., Ishii, M., and Uhle, J., 2004, “LDA Measurement in Air-water Downward Flow,” Experimental Thermal and Fluid Science, 28(4), pp. 317-328.

Sun, X., Kim, S., Cheng, L., Ishii, M., and Beus, S.G., 2004, “Interfacial Structures in Confined Cap-turbulent and Churn-turbulent Flows,” International Journal of Heat and Fluid Flow, 25(1), pp. 44-57.

Sun, X., Paranjape, S., Kim, S., Ozar, B., and Ishii, M., 2004, “Liquid Velocity in Upward and Downward Air-water Flows,” Annals of Nuclear Energy, 31(4), pp. 357-373.

Sun, X., Ishii, M., and J.M. Kelly, 2003, “Modified Two-fluid Model for the Two-group Interfacial Area Transport Equation,” Annals of Nuclear Energy, 30(16), pp. 1601-1622.

Ishii, M., Sun, X., and Kim, S., 2003, “Modeling Strategy of the Source and Sink Terms in the Two-group Interfacial Area Transport Equation,” Annals of Nuclear Energy, 30(13), pp. 1309-1331.

Sun, X., Smith, T.R., Kim, S., Ishii, M., and Uhle, J., 2003, “Interfacial Structure of Air-water Two-phase Flow in a Relatively Large Pipe,” Experiments in Fluids, 34(2), pp. 206-219.

Kim, S., Sun, X., Ishii, M., Beus, S.G., 2003, “Interfacial Area Transport and Evaluation of Source Terms for Confined Air-water Bubbly Flow,” Nuclear Engineering and Design, 219(1), pp. 61-75.

Sun, X., Smith, T.R., Kim, S., Ishii, M., and Uhle, J., 2002, “Interfacial Area of Bubbly Flow in a Relatively Large Diameter Pipe,” Experimental Thermal and Fluid Science, 27(1), pp. 97-109.

Sun, X., Kim, S., Smith, T.R., and Ishii, M., 2002, “Local Liquid Velocity Measurements in Air-water Bubbly Flow,” Experiments in Fluids, 33(5), pp. 653-662.

Sun, X., Dai, Z., and Xu, J., 1997, “Experimental Study on Flow Rate Measurement of Fluid in Tube Using Temperature Fluctuation Cross-Correlation Principle,” Journal of Shanghai Jiao Tong University (In Chinese), 31(2), pp. 51-55.

Sun, X., Xu, J., and Xu, X., 1996, “Bifurcation Theory and Its Application in the Study of Two-phase Flow Instability in Thermal Dynamic Systems, Journal of Shanghai Jiao Tong University (In Chinese), 30(9), pp. 103-109.

 

 

Refereed Full-length Conference Papers and Summaries:

Liu, Q., Diaz, J., Petrov, V., Burak, A., Manera, A., Kelly, J., and Sun, X., “Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section,” Proc. of the 2021 International Conference on Nuclear Engineering (ICONE21), August 4–6, 2021, Virtual Conference, Online, submitted.

Zhang, S., Wu, X., and Sun, X., “Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-cooled High-Temperature Reactors,” Proc. of the 2020 28th International Conference on Nuclear Engineering, Joint with the ASME 2020 Power Conference (ICONE28-POWER2020), August 2-6, 2020, Virtual Conference, Online (Best Paper in the Student Paper Competition: North America Award).

Lin, H.C., Hu, R., and Sun, X., “Validating System Analysis Module (SAM) Models Using Natural Circulation Experimental Data,” Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), August 18-22, 2019, Portland, OR, paper ID 28331, pp. 4457-4469.

Liu, Y., Sun, X., Liu, Y., and Dinh, N., “Uncertainty Quantification and Reduction for Multiphase-CFD Solvers: A Data-Driven Bayesian Approach Supported by High-Resolution Local Measurements,” Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), August 18-22, 2019, Portland, OR, paper ID 27546, pp. 3982-3597.

Liu, Y., Qian, Y., Wang, C., Sun, X., and Liu, Y., “Uncertainty Analysis of PIV Measurements for Liquid Velocity in Two-Phase Bubbly Flows,” Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), August 18-22, 2019, Portland, OR, paper ID 27875, pp. 3955-3967.

Zhang, G., Chen, M., and Sun, X., “Transient Analysis of an FHR Coupled to a Helium Brayton Power Cycle,” Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), August 18-22, 2019, Portland, OR, paper ID 27883, pp. 3908-3921.

Cheng, K., Huai, X., Guo, J., and Sun, X., “Experimental Study of Thermal-Hydraulic Performance of a Printed Circuit Heat Exchanger,” Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), August 18-22, 2019, Portland, OR, paper ID 29867, pp. 688-700.

Zhang, S., Lin, H.C., Cheng, K. and Sun, X., “Design of a Direct Reactor Auxiliary Cooling System (DRACS) Considering Tritium Management for Advanced High-Temperature Reactor (AHTR),” Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), August 18-22, 2019, Portland, OR, paper ID 27449, pp. 2878-2891.

Liu, Y., Shi, S., Qian, Y., Sun, X., and Dinh, N, “Inverse Uncertainty Quantification of Turbulence Modeling in Multiphase-CFD Solver using High-resolution Data from Particle Image Velocimetry,” Proceedings of Advances in Thermal Hydraulics 2018 (ATH 2018), Embedded Topical Meeting to ANS Winter Meeting, November 11-15, 2018, Orlando, FL, pp. 1028-1040.

Shi, S., Qian, Y., Wang, D., Liu, Y., and Sun, X., “Liquid-phase Turbulence Measurements in Air-water Two-phase Flows Using Particle Image Velocimetry,” Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), October 14-18, 2018, Qingdao, China (Conference Best Paper Award).

Wang, C., Sun, X., Shi, S., and Christensen, R.N., “Multiphysics Simulation of Graphite Chronic Corrosion by Steam in HTGRs,” Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), October 14-18, 2018, Qingdao, China.

Wu, X., Chan, W., Shi, S., Sun, X., and Christensen, R., “Computational Simulation of Hydrogen Permeation Experiment,” Proceedings of the 26th International Conference on Nuclear Engineering (ICONE-26), July 22-26, 2018, London, England, Paper ID: ICONE26-82487.

Lin, H.S., Zhang, S., Shi, S., Sun, X., Christensen, R., “Transient Modeling of Advanced High Temperature Reactor (AHTR) In RELAP5/SCDAPSIM/MOD 4.0,” Proceedings of the 26th International Conference on Nuclear Engineering (ICONE-26), July 22-26, 2018, London, England, Paper ID: ICONE26-81874.

Lin, H.S., Zhang, S., Lv, Q., Shi, S., Sun, X., Yoder, G., Perez, M., and Allison, C.M., “Modeling of DRACS Test Facility and Advanced High Temperature Reactor (AHTR) using RELAP5/SCDAPSIM/MOD 4.0,” 38th Annual Conference of the Canadian Nuclear Society and 42nd Annual CNS/CNA Student Conference, Saskatoon, SK, Canada, June 3-6, 2018.

Chen, M., Sun, X., and Christensen, R.N., “Numerical Investigation of Thermal Boundary Conditions of a High-Temperature PCHE with Zigzag Flow Channels,” Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018), Charlotte, NC, April 8-11, 2018, pp. 835-843.

Zhang, X., Shi, S., Sun, X., Christensen, R., Anderson, M., and Carlson, M., “Design and Test Plan of a High-Temperature Supercritical CO2 Test Loop for PCHE Type Heat Exchanger Testing,” Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), September 3 – 8, 2017, Xi’an, China, paper ID 21110.

Wang, L., Chen, M., Shi, S., Che, D., and Sun, X., “Multi-objective Optimization of a Printed Circuit Heat Exchanger Design,” Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), September 3 – 8, 2017, Xi’an, China, paper ID 21492.

Zhang, X., Shi, S., Christensen, R., and Sun, X., “Review on Mechanical Design of Printed Circuit Heat Exchangers,” Proceedings of the 25th International Conference on Nuclear Engineering (ICONE-25), July 2-6, 2017, Shanghai, China, Paper ID: ICONE25-67284.

Zhang, S., Shi, S., Wu, X., Sun, X., and Christensen, R., “Double-Wall Natural Draft Heat Exchanger Design for Tritium Control in FHRS,” Proceedings of the 25th International Conference on Nuclear Engineering (ICONE-25), July 2-6, 2017, Shanghai, China, Paper ID: ICONE25-67844.

Shi, S., Zhang, X., Sun, X., and Zhang, H., “Development of Five-Equation Drift Flux Model for Thermal Non-Equilibrium Phenomena in LWRs,” Proceedings of the 25th International Conference on Nuclear Engineering (ICONE-25), July 2-6, 2017, Shanghai, China, Paper ID: ICONE25-67981.

Liu, Q., Shi, S., Wang, L., Sun, X., and Kelly, J., “Thermal Analysis of a Test Facility for Post-CHF Heat Transfer Experiments,” 2017 Japan-U.S. Seminar on Two-Phase Flow Dynamics, June 22-24, 2017, Sapporo, Hokkaido, Japan.

Shi, S., Wang, L., Yin, J., and Sun, X., “Measurement of Liquid-Phase Velocity Field around Taylor Bubbles in Slug Flows,” 2017 Japan-U.S. Seminar on Two-Phase Flow Dynamics, June 22-24, 2017, Sapporo, Hokkaido, Japan.

Shi, S., Sun, X., and Ishii, M., “Initial Startup Procedure Investigation of a BWR-Type Small Modular Reactor,” Proceedings of the International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants, June 06-09, 2017, Vienna, Austria.

Rahnema, F., Petrovic, B., Singh, P., Sun, X., Tsvetkov, P., Yoder, G., Zhang, D., and Zhang, J., “Integrated Approach to Fluoride High Temperature Reactor (FHR) Technology Development,” Proceedings of the 37th Annual Conference of the Canadian Nuclear Society and 41st CNS/CNA Student Conference, June 4-7, 2017, Niagara Falls, ON, Canada.

Yoon, S.-J., O’Brien, J.E., Wegman, K., Sun, X., “Thermal-Hydraulic Performance of Printed Circuit Heat Exchangers: CFD Analysis with Experimental Validation,” Proceedings of the 2016 International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, NV, November 6-10, 2016, pp. 923-935.

Chen, M., O’Brien, J.E., Yoon, S.-J., Christensen, R.N., Sabharwall, P., Sun, X., “Thermal-Hydraulic Performance of a High-Temperature Zigzag-Channel Printed Circuit Heat Exchanger,” Proceedings of the 2016 International Topical Meeting on High Temperature Reactor Technology (HTR 2016), Las Vegas, NV, November 6-10, 2016, pp. 936-944.

Wang, C., Shi. S., Arcilesi, D.J., Sun, , and Christensen, R.N., “Scaling Analysis and Test Facility Design for Steam Ingress Accident in MHTGR,” Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, Korea, October 9-13, 2016, N11A0127.

Chen, M., Sun, , Christensen, R.N., Shi. S., Skavdahl, I., Utgikar, V., and Sabharwall, P., “Design and Testing of Helically-coiled Fluted Tube Heat Exchangers for FHR Applications,” Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, Korea, October 9-13, 2016, N11A0261.

Chen, M., Shi. S., Sun, , Christensen, R.N., Skavdahl, I., Utgikar, V., and Sabharwall, P., “Design and Dynamic Modeling of a Printed Circuit Heat Exchanger for the Next Generation Nuclear Plant,” Proceedings of Advances in Thermal Hydraulics 2016 (ATH’16), Embedded Topical Meeting, New Orleans, LA, June 12-16, 2016, pp. 429-442.

Zhang, X., Sun, X., Christensen, R.N., Shi, S., Anderson, M., and Carlson, M., “Multi-objective Optimization of a PCHE-Type Intermediate Heat Exchanger using Generic Algorithms,” Proceedings to Advances in Thermal Hydraulics 2016 (ATH’16), Embedded Topical Meeting, New Orleans, LA, June 12-16, 2016, pp. 443-456.

Yoon, S.-J., Wegman, K., O’Brien, J., Sabharwall, P., and Sun, X., “An Analytical Methodology to Evaluate Thermal-Hydraulic Performance of Compact Heat Exchangers, Accounting for Heat Loss,” Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17 – 20, 2016, pp. 1081-1090.

Lv, Q., Lin, H.C., Shi, S., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Experimental Study of DRACS Steady-state and Transient Performance,” Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17 – 20, 2016, pp. 640-649.

Liu, Q, Lv, Q., Shi, S., Sun, X., and Kelly, J., “Design of Post-CHF Heat Transfer Experiments for High-Pressure and High-Flow Conditions,” Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17 – 20, 2016, pp. 2229-2245.

Lin, H.C., Lv, Q., Shi, S., Sun, X., Christensen, R., Blue, T., and Sabharwall, P., “RELAP5 Model Validation and Benchmark for DRACS Thermal Performance,” Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016), San Francisco, CA, April 17 – 20, 2016, pp. 650-659.

Zhang, X., Sun, X., Christensen, R.N., Anderson, M., and Carlson, M., “Optimization of S-Shaped Fin Channels in a Printed Circuit Heat Exchanger for Supercritical CO2 Test Loop,” The 5th International Supercritical CO2 Power Cycles Symposium, March 29 – 31, 2016, San Antonio, Texas.

Chen, M., Sun, X., Christensen, R., Skavdahl, I., Utgikar, V., and Sabharwall, P., “Fabrication and Testing of a High-Temperature Printed Circuit Heat Exchanger,” Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30 – September 4, 2015, Chicago, IL, pp. 7621-7636.

Zhang, X., Sun, X., Christensen, R.N. and Anderson, M., “Preliminary Structural Assessment of a Printed Circuit Heat Exchanger with S-shaped Fins,” Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30 – September 4, 2015, Chicago, IL, pp.7673-7686.

Wu, X., Arcilesi, D., Sun, X., Christensen, R., Sabharwall, P., “Conceptual Design of Tritium Removal Facility for FHRs,” Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30 – September 4, 2015, Chicago, IL, pp. 4935-4948.

Haneklaus, N., Kendrick, J., Huddar, L., Zweibaum, N., Peterson, P.F., Hughes, J., Blandford, E., Lv, Q., Sun, X., and Yoder, “Thermal Hydraulic Benchmarking Exercises to Support Fluoride-Salt-Cooled, High-Temperature Reactor (FHR) Licensing,” Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30 – September 4, 2015, Chicago, IL, pp. 6918-6930.

Jentz, I., Anderson, M., and Sun, X., “Modeling the Mechanical Integrity of Airfoil Printed Circuit Heat Exchangers,” Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30 – September 4, 2015, Chicago, IL, pp. 7647-7657.

Lv, Q., Lin, H.C., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Experimental Study of DRACS Thermal Performance in a Low-Temperature Test Facility,” Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30 – September 4, 2015, Chicago, IL, pp. 1645-1658.

Zhou, X., Sun, X. and Liu, Y., “Liquid-phase Turbulence Measurements in Air-Water Two-Phase Flows over a Wide Range of Void Fractions,” 2015 US-Japan Seminar on Two-phase Flow Dynamics, May 10-15, 2015, West Lafayette, IN, Paper No. 2.6.

Doup, B. and Sun, X., “Revised Source/Sink Terms for the Two-Group Interfacial Area Transport Equations,” 2015 US-Japan Seminar on Two-phase Flow Dynamics, May 10-15, 2015, West Lafayette, IN, Paper No. 1.4

Sabharwall, P., O’Brien, J., Yoon, S.J., and Sun, “Experimental Facility for Development of High-Temperature Reactor Technology: Instrumentation Needs and Challenges,” Proceedings of ICAPP 2015, May 03-06, 2015, Nice, France, Paper 15066.

Kim, I.H, Wu, X., Arcilesi Jr., D.J., Sun, X., Christensen, R., and Sabharwall, P., “OSU Tritium Control and Mitigation Strategy for FHRs,” The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, December 14-18, 2014, NUTHOS10-1199.

Wu, X., Kim, I.H., Arcilesi Jr., D.J., Sun, X., Christensen, R., and Sabharwall, P., “Computer Simulation of Tritium Removal Facility Design,” The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, December 14-18, 2014, NUTHOS10-1204.

Zhou, X., Williams, M., Fu, Y., Liu, Y., and Sun, X., “Local Gas- and Liquid-phase Measurements for Air-water Two-phase Flows in a Rectangular Channel,” The 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), Okinawa, Japan, December 14-18, 2014, NUTHOS10-1022.

Mylavarapu, K., Sun, X., and Christensen, R.N., “Hydrodynamically Developing and Fully-Developed Laminar Flows in a Semicircular Duct: Analytical and Computational Analyses,” Advances in Thermal Hydraulics 2014 (ATH’14), Embedded Topical Meeting, Reno, NV, June 15-19, 2014, pp. 377-394.

Doup, B., Zhou, X., and Sun, X., “Development of the Local Relative Velocity Measurements in Bubbly, Cap-Bubbly, and Slug Flows,” Proceedings of International Mechanical Engineering Congress & Exposition (IMECE2013), November 15-21, 2013, San Diego, CA, IMECE2013-66581.

Lv, Q., Chen, M., Sun, X., Christensen, R.N., Blue, T., Yoder, G., Wilson, D., and Sabharwall, P., “Design of Fluidic Diode for a High-temperature DRACS Test Facility,” Proceedings of the 21st International Conference on Nuclear Engineering (ICONE21), July 29-August 2, 2013, Chengdu, China, ICONE21-16902.

Zhou, X., Doup, B., and Sun, X., “Local Relative Velocity Measurements in Air-water Bubbly Flows,” The 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH-15), Pisa, Italy, May 12-15, 2013, NURETH15-

Arcilesi, D.J., Ham, T.K., Sun, X., Christensen, R.N., and Oh, C., “Developmental Analysis for the Operation of a Scaled-down, High-temperature Test Facility for the Experimental Investigation of the Initial Stages of a VHTR Air-ingress Accident,” The 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH-15), Pisa, Italy, May 12-15, 2013, NURETH15-

Lv, Q., Wang, X., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs,” The 15th International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH-15), Pisa, Italy, May 12-15, 2013, NURETH15-

Zhou, X., Doup, B., and Sun, X., “Local Measurements in Air-water Two-phase Turbulent Flows,” Advances in Thermal Hydraulics, 2012, (ATH’12), November 24-28, 2012, San Diego, CA, pp. 287-296.

Arcilesi, D.J., Ham, T.K., Sun, X., Christensen, R.N., and Oh, C., “Scaling and Developmental Analysis for the Construction of a Scaled-down, High-temperature Test Facility for the Experimental Investigation of the Initial Stages of a VHTR Air-ingress Accident,” Advances in Thermal Hydraulics, 2012, (ATH’12), November 24-28, 2012, San Diego, CA, pp. 72-81.

Zhou, X., Doup, B., and Sun, X., “Gas and Liquid Measurements in Air-Water Bubbly Flows,” 2012 International Congress on Advances in Nuclear Power Plants (ICAPP’12), Proceedings of ICAPP’12, Chicago, USA, June 24-28, 2012, Paper 12242.

Zhao, H, Zhang, H., Zou, L. and Sun, X., “Enhancing VHTR Passive Safety and Economy with Thermal Radiation Based Direct Reactor Auxiliary Cooling System,” 2012 International Congress on Advances in Nuclear Power Plants (ICAPP’12), Proceedings of ICAPP’12, Chicago, USA, June 24-28, 2012, Paper 12301.

Doup, B., Zhou, X., and Sun, X., “Local Gas and Liquid Parameter Measurements in Air-water Two-phase Flows,” 2012 Japan-U.S. Seminar on Two-phase Flow Dynamics, June 7-12, 2012, Tokyo, Japan, Paper No. T15.

Flanders, J., Eades, M., Blue, T., and Sun, X., “Heat Exchanger Considerations for a Space Molten Salt Reactor,” Proceedings of Nuclear and Emerging Technologies for Space, NETS 2012, March 21-23, 2012, The Woodlands, TX.

Wang, X., Sun, X., Doup, B., and Zhao, H., “Dynamic Modeling Strategy for Flow Regime Transition in Gas-Liquid Two-Phase Flows,” The 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-14), Toronto, Ontario, Canada, September 25-30, 2011, paper no.: NURETH14-569.

Wang, X. and Sun, X., “CFD Simulations of Cap-bubbly Two-phase Flows Using Two-Group Interfacial Area Transport Equation,” Proceedings of ASME-JSME-KSME Joint Fluids Engineering Conference 2011 (AJK2011-FED), Hamamatsu, Shizuoka, Japan, July 24-29, 2011, paper no.: AJK2011-03024, pp. 1315-1330.

Eades, M., Flanders, J., McMurray, N., Denning, R., Sun, X., Windl, W., and Blue, T., “Space Molten Salt Reactor Concept for Nuclear Electric Propulsion and Surface Power,” Proceedings of Nuclear and Emerging Technologies for Space 2011, NETS 2011, Albuquerque, NM, February 7-10, 2011, Paper 3293; Also published in Journal of the British Interplanetary Society, Vol. 64, No. 6/7, June/July 2011, pp. 186-193.

Utgikar, , Sabharwall, P., and Sun, X., “HTGR Process Heat Application – Nuclear Desalination,” Proceedings of the 5th International Topical Meeting on High Temperature Reactor Technology (HTR2010), Prague, Czech Republic, October 18-20, 2010, Paper 244.

Mylavarapu, K., Sun, X., Christensen, R.N., Glosup, R.E., and Unocic, R.R., “Fabrication and Design Aspects of High-temperature Compact Diffusion Bonded Heat Exchangers,” the 8th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-8), Shanghai, China, October 10-14, 2010, Paper No. N8P0243.

Wang, X. and Sun, X., “Numerical Simulations of Cap-bubbly Flows Using Fluent,” the 8th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-8), Shanghai, China, October 10-14, 2010, Paper No.

Wang, X., Sun, X., and Duval, W.M., “Predictions of Phase Distribution in Liquid-liquid Two-component Flow Using FLUENT,” The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa City, Japan, September 27-October 2, 2009, paper no. N13P1060.

Figley, J., Sun, X., and Hajek, B., “Numerical Investigation of a High-Temperature Counter-flow Compact Heat Exchanger,” The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa City, Japan, September 27-October 2, 2009, paper no. N13P1062.

Wang, X. and Sun, X., “Hyperbolicity of One-Dimensional Two-Fluid Model with Interfacial Area Transport Equations,” 2009 ASME Fluids Engineering Division Summer Meeting and Exhibition, August 2-5, 2009, Vail, Colorado, USA, Paper no. FEDSM2009-78388, pp. 895-906.

Aldemir, T., Mandelli, D., Mangan, L.A., Miller, D.W., Stovsky, M.P., Sun, X., Guarro, S., Yau, M., Bucci, P., Kirschenbaum, J., Johnson, B., Elks, C., Ekici, E., Arndt, S.A., “Dynamic Reliability Modeling of Digital Instrumentation and Control Systems in Nuclear Power Plants,” Sixth American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies (NPIC&HMIT 2009), Knoxville, Tennessee, April 5-9, 2009.

Wang, X. and Sun, X., “Effects of Non-uniform Inlet Conditions and Lift Force on Prediction of Phase Distribution in Upward Bubbly Flows with FLUENT-IATE,” The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), Seoul, Korea, October 5–9, 2008.

Mylavarapu, S., Sun, X., Figley, J., Needler, N., and Christensen, R.N., “Investigation of Printed Circuit Heat Exchanger for VHTRs,” Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology (HTR2008), September 28–October 1, 2008, Washington, DC, HTR2008-58097.

Vasavada, S., Sun, X., Ishii, M., and Duval, W., “Interfacial Area Transport Equation for Simulated Reduced-gravity Two-phase Bubbly Flows,” US-Japan Seminar on Two-phase Flow Dynamics, Santa Monica, CA, September 14–18, 2008.

Yee, S., Stone, S., Chenkovich, J., Blue, T., and Sun, X., “A Coupled Powersim and MCNPX Analysis of Online Reprocessing Requirements for a One-fluid U-233/Th-232 FLiBe Molten Salt Breeder Reactor,” 6th International Energy Conversion Engineering Conference (IECEC), Cleveland, OH, July 28–30, 2008, AIAA-2008-5665.

Vasavada, S., Mi, Y., Sun, X., Ishii, M., and Duval, W., “Objective Flow Pattern Determination for Reduced-Gravity Two-Phase Flows,” 46th AIAA Aerospace Sciences Meeting and Exhibit, Reno, Nevada, January 7–10, 2008, AIAA-2008-0823.

Miller, D.W., Reisi-Fard, M., Sun, X., Blue, T.E., Arndt, S.A., “A Review on Gamma Thermometer Applications in Nuclear Reactors,” Paper presented at Joint 8th Annual IEEE Conference on Human Factors and Power Plants (HFPP) and 13th Annual Workshop on Human Performance/Root Cause/Trending/Operating Experience/and Self Assessment (HPRCT), Monterey, CA, August 26–31, 2007 (not included in the proceedings); The 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-12), September 30-October 4, 2007, Pittsburgh, PA, paper no. 249.

Liu, Y., Hibiki, T., Ishii, M., and Sun, X., “Study of Drag Coefficient in Bubbly Flows,” The 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-12), September 30-October 4, 2007, Pittsburgh, PA, paper no. 184.

Wang, X. and Sun, X., “CFD Simulation of Phase Distribution in Adiabatic Upward Bubbly Flows Using Interfacial Area Transport Equation,” The 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-12), September 30-October 4, 2007, Pittsburgh, PA., paper no. 163.

Wang, X., and Sun, X., “A Numerical Study of Upward Bubbly Flow Using Interfacial Area Transport Equation,” 2007 International Conference on Multiphase Flow, ICMF 2007, Leipzig, Germany, July 9 –13, 2007, paper no. PS6_5.

Buchanan, J.R., Kim, S., Sun, X., and Ishii, M., “Multi-Objective Optimization Applied to the One Group Interfacial Area Transport Equations,” 2007 International Conference on Multiphase Flow, ICMF 2007, Leipzig, Germany, July 9–3, 2007, paper no. PS6_21.

Lopez de Bertodano, M., Sun, X., and Buchanan, J., “A Three-Field Two-Fluid CFD Model with a Lateral Displacement Force for the Cap Bubble Regime in a Duct,” 2007 International Conference on Multiphase Flow, ICMF 2007, Leipzig, Germany, July 9–13, 2007, paper no. S6_Wed_A_30.

Vasavada, S., Sun, X., Ishii, M., and Duval, W., “Experimental and Theoretical Study of Interfacial Area Transport for Reduced-gravity Two-phase Flows,” 45th AIAA Aerospace Sciences Meeting and Exhibit, Reno, Nevada, January 8–11, 2007, AIAA-2007-0338.

Ishii, M., Vasavada, S., Sun, X., and Duval, W., “Investigation of Two-phase Flows in Microgravity Using Ground Based Experiments,” 44th AIAA Aerospace Sciences Meeting and Exhibit, Reno, Nevada, January 9–12, 2006, AIAA-2006-0737.

Ishii, M., Vasavada, S., Sun, X., and Duval, W., “Study of Two-phase Flow in Simulated Microgravity Condition,” AIAA Space 2005 Conference, Long Beach, CA, August 30–September 1, 2005, AIAA-2005-6783.

Ishii, M. and Sun, X., “Interfacial Characteristics of Two-phase Flow,” 2004 Japan/US Seminar on Two-phase Flow Dynamics, Lake Biwa, Japan, December 6–11, 2004.

Ishii, M., Kuran, S., Sun, X., Cheng, L., Xu, Y., Yoon, H.J. and Revankar, S.T., “Experimental Study on Stability of Startup of Natural Circulation BWRs with and without Nuclear Coupling,” 2004 Japan/US Seminar on Two-phase Flow Dynamics, Lake Biwa, Japan, December 6–11, 2004.

Kuran, S., Ishii, M., Sun, X., Cheng, L., Xu, Y., Yoon, H.J. and Revankar, S.T., “Nuclear Coupled Flow Instability Study for Natural Circulation BWR Startup Transient,” The 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8, 2004, Paper No.: N6P002.

Ishii, M. and Sun, X., “New Modeling and Experimental Approaches for Characterization of Two-phase Flow Interfacial Structure,” The 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4–8, 2004, Key Note Lecture, Paper No.: KN-04.

Situ, R., Hibiki, T., Sun, X., Mi, Y., Ishii, M., and Mori, M., “Flow Structure of Subcooled Boiling Flow in an Internally Heated Annulus,” 5th International Conference on Multiphase Flows, ICMF’04, Yokohama, Japan, May 30–June 4, 2004, Paper No.: 388.

Sun, X., Liu, Y., Ozar, B., Ishii, M., and Kelly, J.M., “Study on Drag Coefficients for Two Groups of Bubbles,” 12th International Conference on Nuclear Engineering (ICONE-12), Washington, DC, April 25–29, 2004, Paper Number: ICONE12-49231, pp. 537-543.

Kuran, S., Sun, X., Xu, Y., Yoon, H.J., Cheng, L., Revankar, S.T., Ishii, M., and Wang, W., “Effect of Inlet Flow Resistance on Instabilities during Startup Transient in Natural Circulation BWRs,” 12th International Conference on Nuclear Engineering (ICONE-12), Washington, DC, April 25-29, 2004, Paper Number: ICONE12-49221, pp. 525-535.

Kim, S., Sun, X., and Ishii, M., 2003, “Research on Interfacial Area Transport: the Present and Future Efforts,” The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5–9, 2003, Paper No.: A00406.

Sun, X., Paranjape, S., Kim, S., Ozar, B., and Ishii, M., 2003, “Liquid Velocity in Air-water Upward and Downward Flows,” The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5–9, 2003, Paper No.: A00104.

Sun, X., Ishii, M., and Kelly, J.M., 2003, “Two-fluid Model Consistent with the Two-group Interfacial Area Transport Equation,” The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, 2003, Paper No.: A00405.

Situ, R., Mi, Y., Sun, X., Ishii, M., and Mori, M., 2003, “Bubble Lift-off Size in Forced Convection Subcooled Boiling,” 2003 ASME Summer Heat Transfer Conference, Las Vegas, Nevada, July 21–23, 2003, Paper No.: HT2003-47206.

Sun, X., Paranjape, S., Kim, S., H. Goda, Ishii, M., and Kelly, J.M., 2003, “Local Liquid Velocity in Vertical Air-water Downward Flow,” 8th International Symposium on Gas-liquid Flows, ASME/JSME Joint Fluids Engineering Division Summer Meeting, Honolulu, Hawaii, USA, July 6-10, 2003, Paper Number: FEDSM03-45548, pp. 1673-1683.

Sun, X., Kim, S., Ishii, M., and Beus, S.G., 2003, “Development of Two-group Interfacial Area Transport Equation for Confined Flow—II: Model Evaluation,” 11th International Conference on Nuclear Engineering (ICONE-11), Tokyo, Japan, April 20–23, 2003, Paper Number: ICONE11-36115.

Sun, X., Kim, S., Ishii, M., and Beus, S.G., 2003, “Development of Two-group Interfacial Area Transport Equation for Confined Flow—I: Modeling of Bubble Interactions,” 11th International Conference on Nuclear Engineering (ICONE-11), Tokyo, Japan, April 20–23, 2003, Paper Number: ICONE11-36114.

Sun, X., Kim, S., Cheng, L., Ishii,, and Beus, S.G., 2002, “Development of Interfacial Structure in a Confined Air-water Cap-turbulent and Churn-turbulent Flow,” Proceedings of ICONE 10, Vol. 3, 10th International Conference on Nuclear Engineering (ICONE 10), April 14–18, 2002, Arlington, Virginia, USA Paper No.: ICONE10-22614, pp. 987-996.

Smith, T., Ishii, M., Sun, X., Kim, S., and Uhle, J., 2001, “Interfacial Area Transport in Large Diameter Pipe: 4” and 6”, 4th International Conference on Multiphase Flow, ICMF 2001, New Orleans, Louisiana, USA. May 27 to June 1, 2001, Paper No.: 766.

Kim, S., Sun, X., Ishii, M., and Lincoln F., 2001, “Interfacial Area Transport in a Confined Bubbly Flow,” Proceedings of ICONE 9, 9th International Conference on Nuclear Engineering (ICONE 9), April 8–12, 2001, Nice Acropolis, France, Paper No.: 122.

Kim, S., Sun, X., Ishii, M., and Beus, S.G., 2001, “Development of Gas-liquid two-phase Flow Interfacial Structure in a Confined Bubbly Flow,” Proceedings of ICONE 9, 9th International Conference on Nuclear Engineering (ICONE 9), April 8–12, 2001, Nice Acropolis, France, Paper No.: 121.

Sun, X., Kim, S., Smith, T., Ishii, M., and Uhle, J., 2000, “Interfacial Area Transport of Bubbly Flow in a Relatively Large Pipe,” Proceedings of the 1st International Conference on Mechanical Engineering (ICME 2000), Nov. 20-22, Shanghai, Paper No.: W110.

Sun, X., Smith, T., Kim, S., and Ishii, M., 2000, “Local Measurement of Liquid Velocity in Bubbly Flow,” Proceedings of ICONE 8, 8th International Conference on Nuclear Engineering (ICONE 8), April 2–6, 2000, Baltimore, MD, USA, Paper No.: ICONE-8476, Vol. 6A, pp. 543-552.

Sun, X., Dai, Z., and Xu, J., 1997, “A Prototype of On-line Digital Flow Rate Meter based on Cross-correlation Principle,” Proceedings of the Fifth International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-5), Edited by Chao, J., and Zhou, Y., Beijing, China, April 14–18, 1997, pp. FF2-1–FF2-5.

Sun, X., Dai, Z., Weng, Y., and Xu, J., 1996, “Experimental Study on Flow Rate Measurement by Using Cross-correlation of Temperature Fluctuations,” HTD-Vol. 334, Proceedings of the ASME Heat Transfer Division, Volume 3, 1996 International Mechanical Engineering Congress and Exposition (IMECE), November 17–22, 1996, Atlanta, Georgia, pp.193-199.

Xu, X., Sun, X., and Xu, J., 1996, “Bifurcation Numerical Model of Two-phase Natural Circulation flow Instability Analysis,” Proceedings of 10th Pacific Basin Nuclear Conference, 1, Kobe, Japan, October 20–25, 1996, pp. 402-406.

Sun, X., Dai, Z., Zong, S., Weng, Y., and Xu, J., 1996, “Experimental Study on Flow Rate Measurement System of Fluid Using Temperature Cross-correlation Principle,” Proceedings of 10th Pacific Basin Nuclear Conference, 1, Kobe, Japan, October 20–25, 1996, pp. 446-452.

Xu, X., Xu, J., and Sun, X., 1996, “Study on Two-phase Natural Circulation Flow Instability by Using Bifurcation Theory,” Proceedings of the ASME/JSME 4th International Conference on Nuclear Engineering, Volume 1-Part A: Basic Technological Advances, Edited by Rao, A.S., Duffey, R.B., and Elias, D., ICONE-4, New Orleans, Louisiana, March 10–14, 1996, pp. 291-296.

Summaries:

Arcilesi, D.J., Ham, T.K., Sun, X., Christensen, R.N., and Oh, C, “Oxygen Concentration Measurements During the Initial Stages of an HTGR Double-Ended Guillotine Break,” Transactions of the American Nuclear Society, Vol. 121, ANS Winter Meeting, November 17-21, 2019, pp. 1629-1632, Washington, DC, Summary.

Zhang, S., Lin, H.C., Cheng, K., and Sun, X., “Design of a High-Temperature Fluoride Salt Test Facility (HT-FSTF),” Transactions of the American Nuclear Society, Vol. 121, ANS Winter Meeting, November 17-21, 2019, pp. 1649-1652, Washington, DC, Summary.

Wang, C., Sun, X., and Christensen, R.N., “Multiphysics Simulation of IG-110 Oxidation by Moisture Under MHTGR Normal Operation Conditions,” Transactions of the American Nuclear Society, Vol. 119, ANS Winter Meeting, November 11-15, 2018, pp. 555-558, Orlando, FL, Summary.

Zhang, X., Liu, Y., Sun, X., and Dinh, N., “Design of Validation Experiments for Model Improvement of Dispersed Flow Film Boiling in COBRA-TF,” Transactions of the American Nuclear Society, Vol. 119, ANS Winter Meeting, November 11-15, 2018, pp. 133-136, Orlando, FL, Summary.

Qian, Y., Shi, S., Wang, D., Liu, Y., Yin, J., and Sun, X., “Measurements of Liquid-phase Turbulence in Air-water Two-phase Flows using PIV,” Transactions of the American Nuclear Society, Vol. 118, 2018 ANS Annual Meeting, June 17-21, 2018, pp. 1023-2017, Philadelphia, PA, Summary.

Wang, C., Sun, X., and Christensen, R.N., “Numerical Simulation of Chronic Moisture Graphite Oxidation for MHTGR,” Transactions of the American Nuclear Society, Vol. 118, 2018 ANS Annual Meeting, June 17-21, 2018, pp. 723-726, Philadelphia, PA, Summary.

Zhang, S., Chen, M., Shi, S., Sun, X., and Christensen, R., “Corrosion Behavior of Stainless Steel 316H in LiF-NaF-KF (FLiNaK) at High Temperatures,” Transactions of the American Nuclear Society, Vol. 117, 2017 ANS Winter Meeting, October 29-Novmber 2, 2017, 132-135, Washington, DC, Summary.

Wu, X., Zhang, S., Shi, S., Sun, X., Holcomb, D., Christensen, R., Sabharwall, P., “Tritium Release Limit for Fluoride Salt-cooled High-temperature Reactors,” Transactions of the American Nuclear Society, Vol. 115, 2016 ANS Winter Meeting, November 6-10, 2016, 1059-1062, Las Vegas, NV, Summary.

Skavdahl, I., Utgikar, V., Sabharwall, P., Chen, M., Sun, X., and Christensen, R.N., “Simulation of Advanced High Temperature Reactor Control System using MATLAB,” Transactions of the American Nuclear Society, Vol. 113, 2015 ANS Winter Meeting, November 8-12, 2015, 421-424,Washington, DC, Summary.

Zhang, X., Sun, X., and Christensen, R.N., “Design of an Advanced Intermediate Heat Exchanger for Supercritical CO2 Brayton Cycle,” Transactions of the American Nuclear Society, Vol. 113, 2015 ANS Winter Meeting, November 8-12, 2015, 1393-1396, Washington, DC, Summary.

Skavdahl, I., Utgikar, V., Sabharwall, P., Chen, M., Kim, I.H., Sun, X., and Christensen, R.N., “Transient Analysis of Advanced High Temperature Reactors Using Process Simulation Software,” Transactions of the American Nuclear Society, Vol. 111, 2014 ANS Winter Meeting, November 9-13, 2014, 1087-1089, Anaheim, CA, Summary.

Chen, M., Kim, I., Sun, X., Christensen, R.N., Skavdahl, I., Utgikar, V., and Sabharwall, P., “Preliminary Design of a Helical Coil Heat Exchanger for a Fluoride Salt-Cooled High-Temperature Test Reactor,” Transactions of the American Nuclear Society, Vol. 111, 2014 ANS Winter Meeting, November 9-13, 2014, 1460-1463, Anaheim, CA Summary.

Jentz, I., Marzouk, M.B., Anderson, M., and Sun, X., “System for Testing Thermal Shock in Printed Circuit Heat Exchangers,” Transactions of the American Nuclear Society, Vol. 111, 2014 ANS Winter Meeting, November 9-13, 2014, 107-110, Anaheim, CA, Summary.

Ham, T.K., Arcilesi, D.J., Kim, I., Sun, X., Christensen, R.N., and Oh, C., “On the Effects of Containment Design to GT-MHR Air-Ingress,” Transactions of the American Nuclear Society, Vol. 109, 2013 ANS Winter Meeting, November 10-14, 2013, Washington, DC, pp. 316-319, Summary.

Bartel, N., Utgikar, V., Sabharwall, P., Chen, M., Sun, X., Christensen, R.N., and Kim, I.H., “Transient Model of Wavy-Channel Printed Circuit Heat Exchangers,” Transactions of the American Nuclear Society, Vol. 109, 2013 ANS Winter Meeting, November 10-14, 2013, Washington, DC, pp. 291-294, Summary.

Chen, M., Kim, I., Sun, X., Christensen, R.N., Bartel, N., Utgikar, V., and Sabharwall, P., “Dynamic Response Analysis of a Scaled-Down Offset Strip-Fin Intermediate Heat Exchanger,” Transactions of the American Nuclear Society, Vol. 109, 2013 ANS Winter Meeting, November 10-14, 2013, Washington, DC, pp. 270-273, Summary.

Lv, Q., Kim, I., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Validation of a MATLAB Code Developed for DRACS Thermal Performance Evaluation,” Transactions of the American Nuclear Society, Vol. 109, 2013 ANS Winter Meeting, November 10-14, 2013, Washington, DC, pp. 1695-1698, Summary.

Eades, M., Sun, X., and Blue, T., “Molten Salt Technology for Very High Flux Research Reactors,” Transactions of the American Nuclear Society, Vol. 108, 2013 American Nuclear Society Annual Meeting, June 16-20, 2013, Atlanta, GA, pp. 904-907, Summary.

Kim, I., Sun, X., and No, H.C., “CFD Study of Thermal-Hydraulic Performance of a PCHE under FLiNaK-Helium Condition,” Transactions of the American Nuclear Society, Vol. 108, 2013 American Nuclear Society Annual Meeting, June 16-20, 2013, Atlanta, GA, pp. 1079-1081, Summary.

Bartel, N., Utgikar, V., Sabharwall, P., Chen, M., Sun, X., Christensen, R.N., and Kim, I.H., “Thermal-Hydraulic Design of Wavy-Channel Printed Circuit Heat Exchanger for Advanced Reactors,” Transactions of the American Nuclear Society, Vol. 108, 2013 American Nuclear Society Annual Meeting, June 16-20, 2013, Atlanta, GA, pp. 1086-1089, Summary.

Chen, M., Kim, I., Sun, X., Christensen, R.N., Bartel, N., Utgikar, V., and Sabharwall, P., “Design of Printed Circuit Heat Exchanger for Very High Temperature Reactors,” Transactions of the American Nuclear Society, Vol. 108, 2013 American Nuclear Society Annual Meeting, June 16-20, 2013, Atlanta, GA, pp. 1090-1093, Summary.

Lv, Q., Adams, I., Wang, X., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “A MATLAB Code for Thermal Performance Evaluation of a Low-Temperature DRACS Test Facility,” Transactions of the American Nuclear Society, Vol. 107, 2012 American Nuclear Society Winter Meeting, November 11-15, 2012, San Diego, CA, pp. 1374-1377, Summary.

Ham, T.K., Arcilesi, D.J., Sun, X., Christensen, R.N., Oh, C., and Kim, E.S., “Preliminary CFD Calculations for OSU Air-Ingress Experimental Facility,” Transactions of the American Nuclear Society, Vol. 107, 2012 American Nuclear Society Winter Meeting, November 11-15, 2012, San Diego, CA, pp. 1290-1292, Summary.

Arcilesi, D.J., Ham, T.K., Sun, X., Christensen, R.N., and Oh, C., “Heat Transfer Characterization for a Scaled-down Air-ingress Accident Test Facility,” Transactions of the American Nuclear Society, Vol. 106, 2012 American Nuclear Society Annual Meeting, June 24-28, 2012, Chicago, IL, pp. 1081-1084, Summary.

Lv, Q., Wang, X., Adams, I., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Design of a Scaled-down Low-temperature DRACS Test Facility for an AHTR,” Transactions of the American Nuclear Society, Vol. 106, 2012 American Nuclear Society Annual Meeting, June 24-28, 2012, Chicago, IL, pp. 1071-1074, Summary.

Arcilesi, D.J., Ham, T.K., Sun, X., Christensen, R.N., and Oh, C., “Density-Driven Air Ingress and Hot Plenum Natural Circulation for a VHTR,” Transactions of the American Nuclear Society, Vol. 105, 2011 American Nuclear Society Winter Meeting, October 30-November 3, 2011, Washington, DC, pp. 990-992, Summary.

Arcilesi, D.J., Ham, T.K., Sun, X., Christensen, R.N., and Oh, C., “Development of Scaling Analysis for Air Ingress Experiments for a VHTR,” Transactions of the American Nuclear Society, Vol. 105, 2011 American Nuclear Society Winter Meeting, October 30-November 3, 2011, Washington, DC, pp. 987-989, Summary.

Doup, B. and Sun, X., “Two-Phase Flow Parameter Measurements in Vertical Air-Water Flows,” Transactions of the American Nuclear Society, Vol. 105, 2011 American Nuclear Society Winter Meeting, October 30-November 3, 2011, Washington, DC, pp. 919-921, Summary.

Wang, X., Lv, Q., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Design of a Scaled-down DRACS Test Facility for an AHTR,” Transactions of the American Nuclear Society, Vol. 105, 2011 American Nuclear Society Winter Meeting, October 30-November 3, 2011, Washington, DC, pp. 1031-1034, Summary.

Wang, X., Lv, Q., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs,” Transactions of the American Nuclear Society, Vol. 105, 2011 American Nuclear Society Winter Meeting, October 30-November 3, 2011, Washington, DC, pp. 1027-1030, Summary.

Aldemir, T., Catalyurek, U., Denning, R., Smidts, C., Sun, X., and Yilmaz, A., “Method and Tool Development to Support Systematic Quantification of Uncertainties,” Transactions of the American Nuclear Society, Vol. 104, 2011 American Nuclear Society Annual Meeting, Hollywood, FL, June 26-30, 2011, pp. 954-956, Summary.

Mylavarapu, K., Sun, X., Glosup, R.E., Christensen, R.N., Castle, B., and Patterson, M.W., “Experiments in High-temperature Helium Facility: Experimental Data Reduction, Uncertainty Analysis, and Thermal-Hydraulic Correlations,” Transactions of the American Nuclear Society, Vol. 104, 2011 American Nuclear Society Annual Meeting, Hollywood, FL, June 26-30, 2011, pp. 975-977, Summary.

Wang, X., Lv, Q., Sun, X., Christensen, R.N., Blue, T.E., Yoder, G., Wilson, D., and Sabharwall, P., “A Modular Design of a Direct Reactor Auxiliary Cooling System for AHTRs,” Transactions of the American Nuclear Society, Vol. 104, 2011 American Nuclear Society Annual Meeting, Hollywood, FL, June 26-30, 2011, pp. 1077-1080, Summary.

Zhou, X. and Sun, X., “Velocity Measurements in Gas-liquid Two-phase Slug and Churn-turbulent Flows,” Transactions of the American Nuclear Society, Vol. 104, 2011 American Nuclear Society Annual Meeting, Hollywood, FL, June 26-30, 2011, pp. 1091-1093, Summary.

Wang, X. and Sun, X., “Predictions of Cap-bubbly Flows with the Two-group Interfacial Area Transport Equation,” Transactions of the American Nuclear Society, Vol. 103, 2010 American Nuclear Society Winter Meeting, Las Vegas, NV, November 7-11, 2010, pp. 936-938, Summary.

Wang, X., H. Zhang, and Sun, X., “On the Cooling of Nuclear Power Plants,” Transactions of the American Nuclear Society, Vol. 102, 2010 American Nuclear Society Annual Meeting, San Diego, CA, June 13-17, 2010, pp. 664-666, Summary.

Mylavarapu, K., Sun, X., Christensen, R.N., and Vaughn, J., “On the Diffusion Bonding of Alloy 617 for High-Temperature Compact Heat Exchangers,” Transactions of the American Nuclear Society, Vol. 101, 2009 American Nuclear Society Winter Meeting, Washington, DC, November 15-19, 2009, pp. 370-372, Summary.

Mylavarapu, K., Unocic, R.R., Sun, X., Christensen, R.N., “On the Microstructural and Mechanical Characterization of Diffusion Bonded Alloy 617 Plate Specimens for High-Temperature Compact Heat Exchangers,” Transactions of the American Nuclear Society, Vol. 101, 2009 American Nuclear Society Winter Meeting, Washington, DC, November 15-19, 2009, pp. 367-369, Summary.

Aldemir, T., Guarro, S., Kirschenbaum, J., Mandelli, D., Mangan, L.A., Bucci, P., Yau, M., Johnson, B., Elks, C., Ekici, E., Stovsky, M.P., Miller, D.W., Sun, X., Arndt, S.A., “Dynamic Reliability Modeling of Digital Instrumentation and Control Systems in Nuclear Power Plants,” Transactions of the American Nuclear Society, Vol. 100, 2009 American Nuclear Society Annual Meeting, Atlanta, GA, June 14-18, 2009, pp. 205-207, Summary.

Wang, X., Sun, X., and W. Duval, “Predictions of Phase Distribution in Liquid-liquid Two-component Flow Using FLUENT-IATE,” Transactions of the American Nuclear Society, Vol. 100, 2009 American Nuclear Society Annual Meeting, Atlanta, GA, June 14-18, 2009, pp. 695-696, Summary.

Wang, X. and Sun, X., “The Well-posedness of Incompressible One-dimensional Two-fluid Model with the Inclusion of the Interfacial Area Transport Equations,” Transactions of the American Nuclear Society, Vol. 100, 2009 American Nuclear Society Annual Meeting, Atlanta, GA, June 14-18, 2009, pp. 729-731, Summary.

Mylavarapu, S., Sun, X., and Christensen, R.N., “Photofabrication and Surface Roughness of Flow Channels for a Compact High-Temperature Heat Exchanger,” Transactions of the American Nuclear Society, Vol. 99, 2008 ANS Winter Meeting, Reno, NV, November 9-13, 2008, pp. 837-839, Summary.

Yee, S., Blue, T., and Sun, X., “Online Fuel Reprocessing of a Liquid Fluoride Reactor,” Transactions of the American Nuclear Society, Vol. 98, 2008 ANS Annual Meeting, Anaheim, CA, June 8–12, 2008, pp. 717-718, Summary.

Yee, S., Piet, S.J., and Sun, X., “Dynamic Modeling of the Nuclear Fuel Cycle without Calling Reactor Physics Models,” Transactions of the American Nuclear Society, Vol. 98, 2008 ANS Annual Meeting, Anaheim, CA, June 8–12, 2008, pp. 129-130, Summary.

Wang, X. and Sun, X., “Effects of Inlet Boundary Condition Profiles on Predictions of Interfacial Area Concentration in FLUENT with IATE,” Transactions of the American Nuclear Society, Vol. 98, 2008 ANS Annual Meeting, Anaheim, CA, June 8–12, 2008, pp. 455-456, Summary.

Vasavada, S., Sun, X., Ishii, M., and Duval, W., “Determination of Drag Coefficient and Rise Velocity of Ellipsoidal and Distorted Drops,” Transactions of the American Nuclear Society, Vol. 98, 2008 ANS Annual Meeting, Anaheim, CA, June 8–12, 2008, pp. 552-554, Summary.

Mylavarapu, S., Figley, J., Sun, X., Christensen, R.N., Needler, N., and Hajek, B.K., “Development and Testing of Printed Circuit Heat Exchanger for Generation IV Reactors,” Transactions of the American Nuclear Society, Vol. 98, 2008 ANS Annual Meeting, Anaheim, CA, June 8–12, 2008, pp. 626-627, Summary.

Smith, S.E., Ford, A., Fentiman, A.W., and Sun, X., “MCNP Simulation of Neutron Energy Spectra,” Transactions of the American Nuclear Society, Vol. 96, 2007 ANS Annual Meeting, Boston, MA, June 24–28, 2007, pp. 165-166, Summary.

Wang, X., Christensen, R.N., Blue, T.E., and Sun, X., “Numerical Simulation of Printed Circuit Heat Exchanger Design for a Molten Salt Reactor,” Transactions of the American Nuclear Society, Vol. 96, 2007 ANS Annual Meeting, Boston, MA, June 24–28, 2007, pp. 566-567, Summary.

Wang, X. and Sun, X., “Preliminary Results of Implementation of Interfacial Area Transport Equation,” Transactions of the American Nuclear Society, Vol. 96, 2007 ANS Annual Meeting, Boston, MA, June 24–28, 2007, pp. 591-592, Summary.

Vasavada, S., Sun, X., Ishii, M., and Duval, W., “Two-Phase Flow Structures under Simulated Microgravity Condition,” Transactions of the American Nuclear Society, Vol. 94, 2006 ANS Annual Meeting, Reno, Nevada, June 4–8, 2006, pp. 441-443, Summary.

Lopez de Bertodano, M., Sun, X., Ishii, M., and Ulke, A., “Turbulent Diffusivity Force for the Two-fluid Model in the Cap Bubble Regime,” Transactions of the American Nuclear Society, Vol. 90, 2004 ANS Annual Meeting, Pittsburgh, Pennsylvania, June 13–17, 2004, pp. 577-578, Summary.

Choi, S.W., Vasavada, S., Kim, S., Sun, X., Ishii, M., and Beus. S.G., “Flow Structure in a Two-phase Planar Jet,” Transactions of the American Nuclear Society, Vol. 90, 2004 ANS Annual Meeting, Pittsburgh, Pennsylvania, June 13-17, 2004, pp. 489-491, Summary.

Xu, Y., Sun, X., Kuran, S., Cheng, L., Yoon, H.J., Revankar, S.T., Ishii, M., and Wang, W., “Thermal-hydraulic Instability Study for Natural Circulation BWR Startup in PUMA Facility,” Transactions of the American Nuclear Society, Vol. 89, 2003 ANS/ENS Winter Meeting, New Orleans, Louisiana, November 16–20, 2003, pp. 84-85, Summary.

Kuran, S., Sun, X., and Ishii, M., “Void-reactivity Feedback Simulation for Nuclear-coupled Instability Experiments,” Transactions of the American Nuclear Society, Vol. 89, 2003 ANS/ENS Winter Meeting, New Orleans, Louisiana, November 16-20, 2003, pp. 479-480, Summary.

Kuran, S., Sun, X., and Ishii, M., “Nonlinear Dynamics for Nuclear-coupled Density Wave Oscillations in Natural Circulation BWRs,” Transactions of the American Nuclear Society, Vol. 89, 2003 ANS/ENS Winter Meeting, New Orleans, Louisiana, November 16–20, 2003, pp. 86-87, Summary.

Sun, X., Kuran, S., and Ishii, M., “Cap Bubbly-to-Slug Flow Regime Transition in a Vertical Annulus,” Transactions of the American Nuclear Society, Vol. 89, 2003 ANS/ENS Winter Meeting, New Orleans, Louisiana, November 16–20, 2003, pp. 421-423, Summary.

Sun, X., Kim, S., Ishii, M., Beus, S.G., and Lincoln, F.W., 2002, “Cap Bubble Drift Velocity in a Confined Flow Channel,” Transactions of the American Nuclear Society, Vol. 87, 2002 ANS Winter Meeting, Washington, DC, November 17–21, 2002, pp. 246-247, Summary.

Sun, X., Kim, S., Ishii, M., and Beus, S.G., 2002, “Two-group Interfacial Area Transport Equation for a Confined Test Section,” Transactions of the American Nuclear Society, Vol. 87, 2002 ANS Winter Meeting, Washington, DC, November 17-21, 2002, pp. 238-239, Summary.

Smith, T., Sun, X., and Ishii, M., 1999, “Flow Regimes and Two-phase Phenomena in a Large Pipe,” Transactions of the American Nuclear Society, Vol. 81, 1999 ANS Winter Meeting, Long Beach, California, November 14–18, 1999, pp. 353-354, Summary.

Sun, X., Smith, T., Assad, A., and Ishii, M., 1999, “Measurement of Interfacial Area Concentration in a Large Pipe,” Transactions of the American Nuclear Society, Vol. 81, 1999 ANS Winter Meeting, Long Beach, California, November 14–18, 1999, pp. 341-342, Summary.