PUBLISHED WORK

Peer-reviewed Publications

• S. Zhang, S. Che, A. Burak, and X. Sun, “Initial Operation of a High-Temperature Fluoride Salt Test Facility (FLUSTFA): Issues Identified and Paths Forward,” the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics(NURETH20), Washington DC, USA, August 20-25 (2023). 

• S. Zhang, H.C. Lin, M. Chen, S. Shi, S. Che, A. Burak, X. Sun, and Q. Lv, “Design and Construction of an Integral-Effect Test Facility FLUSTFA for Molten Salt Reactor Applications,” the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH20), Washington DC, USA, August 20-25 (2023). 

• S. Che, S. Zhang, A. Burak, and X. Sun, “FLiNaK Salt Dehydration Plan for Thermal-Hydraulic Experiments,” International Congress on Advances in Nuclear Power Plants (ICAPP), Gyeongju, Korea, April 23-27 (2023).

• S. Zhang and X. Sun, “Mixed Convective and Radiative Heat Transfer of LiF-BeF2-ThF4-UF4 in a Vertical Circular Tube,” Annals of Nuclear Energy, 185, 109706 (2023). 

• S. Zhang and X. Sun, “Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural Circulation Loop,” Nuclear Science and Engineering, DOI: doi.org/10.1080/00295639.2022.2102389 (2022).

• S. Zhang and X. Sun, “Evaluation of Mitigation Strategies for Radioactive Fission Gases in Fluoride-Salt-Cooled High-Temperature Reactors,” Annals of Nuclear Energy, 176, 109289 (2022).

• S. Zhang, “Mixed Convective Heat Transfer of Medium-Prandtl-Number Fluids in Circular Tubes,” International Journal of Heat and Mass Transfer, 190, 122740 (2022).

• S. Zhang and X. Sun, “Convective Heat Transfer and Friction Factor Characteristics of Molten Salts in Spirally Fluted Tubes,” Thermal Science and Engineering Progress, 30, 101264 (2022).

• S. Zhang and X. Sun, “Modeling of a Nitrate Salt Natural Circulation Loop,” Advances in Thermal Hydraulics (ATH), Anaheim, CA, June 12-16 (2022).

• S. Zhang and X. Sun, “Heat Transfer Characteristics of Molten Salts in the Laminar Flow Regime in Circular Horizontal Pipes,” the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Brussels, Belgium, March 6 -11 (2022).

• S. Zhang, S. Che, A. Burak, and X. Sun, “Review of High-Temperature Centrifugal Pumps for Molten Salt Applications,” the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Brussels, Belgium, March 6 -11 (2022).

• S. Zhang and X. Sun, “Experimental Investigation on Measurement Uncertainty of Transit-Time High-Temperature Ultrasonic Flow Meters,” the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Brussels, Belgium, March 6 -11 (2022).

• S. Che, S. Zhang, A. Burak, and X. Sun, “Thermal-Hydraulic Performance of A Printed Circuit Heat Exchanger with Semi-Circular Zigzag Flow Channels for Molten Salt Reactors,” the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Brussels, Belgium, March 6 -11 (2022).

• S. Che, S. Zhang, A. Burak, and X. Sun, “Structural Integrity Assessment of a Unit Cell in a Laboratory-Scale Printed Circuit Heat Exchanger for Molten Salt Reactors with Supercritical CO2 Power Cycle,” Proceedings of the ASME 2021 Pressure Vessels & Piping Conference, Virtual Conference, July 12-16 (2021).

• S. Zhang and X. Sun, “Convective and Radiative Heat Transfer in Molten Salts,” Nuclear Technology, DOI: doi.org/10.1080/00295450.2020.1749481 (2020).

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

• S. Zhang, X. Wu, and X. Sun, “Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-Cooled High-Temperature Reactors,” ASME’s Nuclear Engineering Conference powered by ICONE, Virtual Conference, August 4-5 (2020). 

• A. Burak, S. Zhang, X. Sun, “Development of Experimental Vehicle Technology for the Versatile Test Reactor to Investigate the Effects of Fast Neutron Irradiation on Molten Salts,” 2020 TMS Annual Meeting & Exhibition, San Diego, California, USA, February 23-27 (2020). 

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

• S. Zhang, H.C. Lin, K. Cheng, and X. Sun, “Design of A Direct Reactor Auxiliary Cooling System (DRACS) Considering Tritium Management for Advanced High-Temperature Reactor (AHTR),” Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, August 18-23, pp. 2878-2891 (2019). 

• S. Zhang, H.C. Lin, K. Cheng, and X. Sun, “Design of A High-Temperature Fluoride Salt Test Facility (HT-FSTF),” Transactions of the American Nuclear Society, 121, pp. 1649-1652 (2019).  

• S. Zhang, X. Wu, S. Shi, X. Sun, and R. Christensen, “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 (2018).

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

• H.C. Lin, S. Zhang, S. Shi, X. Sun, R. Christensen, “Transient modeling of Advanced high temperature reactor (AHTR) in RELAP5/SCDAPSIM/MOD 4.0,” Proceedings of the 2018 26th International Conference on Nuclear Engineering, ICONE26, London, England, July 22-28 (2018).

• H.C. Lin, S. Zhang, Q. Lv, S. Shi, X. Sun, G. Yoder, M. Perez, and C.M. Allison, “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 42th Annual CNS/CAN Student Conference, Saskatoon, SK, Canada, June 3 – 6 (2018).

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

• S. Zhang, M. Chen, S. Shi, X. Sun, and R. Christensen, “Corrosion Behavior of Stainless-Steel SS 316H in LiF-NaF-KF (FLiNaK) at High temperatures,” Transactions of the American Nuclear Society, 117, pp. 132-135 (2017).

• X. Wu, S. Zhang, S. Shi, X. Sun, D. Holcomb, R. Christensen, and P. Sabharwall, “Tritium Release Limit for Fluoride Salt-cooled High-temperature Reactors,” ANS Winter Meeting & Expo, Las Vegas, NV, November 6 – 10 (2016).

• S. Zhang, H. Gu, Y. Chen, X. Zhou, G. Liu, “Experimental and Numerical Investigations of Natural Convection in a Vertical Annulus,” Nuclear Power Engineering, 36, pp. 14-17 (2015).

• S. Zhang and H. Gu, “The Effect of Drive Rod’s Location on the Axial Heat Transfer of CRDM,” Chinese Journal of Nuclear Science and Engineering, 35, pp. 439-444 (2015).

• X. Zhou, F. Wang, G. Liu, S. Lin, F. Mao, Y. Zhan, S. Zhang, and H. Gu, “Heat transfer mechanism and thermal sleeve performance of control rod drive mechanism,” Atomic Energy Science and Technology, 49, pp. 2245-2250 (2015).

• S. Zhang and H. Gu, “Experimental and Theoretical Analysis on Axial Heat Transfer Characteristics of CRDM,” Atomic Energy Science and Technology, 48, pp. 1992-1997 (2014).

• Y. You, S. Zhang, and F. Niu, “Scaling Analysis for Mixing in Large Stratified Volumes of Passive Containment,” 2011 Academic Annual Meeting of China Nuclear Society, Beijing, China, October 11-14 (2012).

​

​Invited Presentations/Posters in Workshops

• S. Che, S. Zhang, Y. Liu, M. Chen, A. Burak, and X. Sun, “High-Temperature Molten Salt Test Facilities at UM Thermal Hydraulics Laboratory,” poster session, Molten Salt Reactor Workshop 2023, Oak Ridge National Laboratory, Oak Ridge, TN, October 25-26 (2023).

• D.J. Arcilesi, S. Zhang, R. Christensen, and X. Sun, “Scaling Analysis in Thermal-Hydraulic Experiment Design for SMR Development,” presentation session, Nuclear Scaling and Applications Workshop (NuSAW), Corvallis, Oregon, August 1-3 (2023)

• S. Zhang, H.C. Lin, M. Chen, X. Sun, R. Christensen, S. Garimella, G. Yoder, and E. Dominguez-Ontiveros, “Double-wall Fluted-tube Heat Exchanger (DWFT-HX) Design Considering Tritium Control for FHRs,” poster session, Enabling the Next Nuclear: FHRs to Megawatts, Falls Church, Virginia, December 12-13 (2018). 

• H.C. Lin, S. Zhang, X. Sun, R. Christensen, G. Yoder, and E. Dominguez-Ontiveros, “Thermal Hydraulics Code Validation and Transient Analysis for AHTR,” poster session, Enabling the Next Nuclear: FHRs to Megawatts, Falls Church, Virginia, December 12-13 (2018). 

• M. Chen, S. Zhang, X. Sun, R. Christensen, and G. Yoder, “Design, Fabrication, and Construction of High-Temperature Fluoride Salt Test Facilities for FHR Application,” poster session, ANS Winter Meeting & Expo, Washington, D.C., October 29 – November 2 (2017).

• X. Sun, H.C. Lin, and S. Zhang, “Natural Circulation Salt Heat Transfer,” presentation session, Molten Salt Reactor Workshop 2017, Oak Ridge National Laboratory, Oak Ridge, TN, October 3-4 (2017).

• T. Flaspoehler, B. Petrovic, X. Wu, S. Zhang, R. Christensen, and X. Sun, “Tritium Management in FHRs,” presentation session, Workshop on Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors, Salt Lake City, UT, October 27-28 (2015).