2025年：
1. Z. Li, S. Zhang*, and X. Yang*, “Evaluation and Development of Nusselt Number and Friction Factor Correlations for Airfoil-fin Printed Circuit Heat Exchangers,” International Journal of Heat and Mass Transfer, 253, 127512 (2025).
2. Z. Li, S. Zhang*, and X. Yang*, “A Comprehensive Review of Printed Circuit Heat Exchangers: Fabrication, Thermal-Hydraulic Performance, and Reliability,” Energies, 18(23), 6200 (2025).
3. Z. Li, S. Zhang*, and X. Yang, “Evaluation and Development of Heat Transfer and Friction Factor Correlations for zigzag-channel Printed Circuit Heat Exchangers,”Proceedings of the 2025 32th International Conference on Nuclear Engineering, Volume 16, ICONE26, Weihai, Shandong, China, June 22-26 (2025), DOI : 10.1007/978-981-95-3449-4.
4. S. Zhang*, “Gaussian Process Regression for Predictions of Mixed Convection in Horizontal Pipe Flows,” International Journal of Heat and Mass Transfer, 253, 127614 (2025).
5. A. Burak*, S. Che, D. Barth, B. Haugh, D. Holcomb, L. Prokopchak, K. Robb, V. Rojas, S. Zhang, and X. Sun, “Root Cause Analysis of a Molten Salt Pump in FLUSTFA,” Nuclear Engineering and Design, 444, 114365 (2025).
2024年：
1. S. Zhang*, S. Che, A. Burak, and X. Sun*, “Operation Experience of a High-Temperature Fluoride Salt Test Facility (FLUSTFA): Issues Identified and Paths Forward,” Nuclear Engineering and Design, 429, 113568 (2024).
2. S. Zhang*, S. Che, A. Burak, and X. Sun, “Operation Experience of a High-Temperature Fluoride Salt Test Facility (FLUSTFA): Issues Identified and Paths Forward,” Nuclear Engineering and Design, 429, 113568 (2024).
3. S. Che, S. Zhang, A. Burak, and X. Sun, “Thermal Dehydration Tests of FLiNaK Salt suitable for Thermal-Hydraulic Experiments,” Nuclear Engineering and Technology, https://doi.org/10.1016/j.net.2024.01.037 (2024).
2023年：
1. 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).
2. 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).
3. 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).
4. 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).
2022年：
1. 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).
2. 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).
3. S. Zhang*, “Mixed Convective Heat Transfer of Medium-Prandtl-Number Fluids in Circular Tubes,” International Journal of Heat and Mass Transfer, 190, 122740 (2022).
4. 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).
5. S. Zhang and X. Sun, “Modeling of a Nitrate Salt Natural Circulation Loop,” Advances in Thermal Hydraulics (ATH), Anaheim, CA, June 12-16 (2022).
6. 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).
7. 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).
8. 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).
9. 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).
2021年：
1. 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).
2020年
1. S. Zhang and X. Sun, “Convective and Radiative Heat Transfer in Molten Salts,” Nuclear Technology, DOI: doi.org/10.1080/00295450.2020.1749481 (2020).
2. 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).
3. 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).
4. 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).
2019年：
1. 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).
2. 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).
3. 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).
2018年:
1. 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).
2. 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).
3. 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).
4. 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).
2017年：
1. 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).
2. 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).
2016年：
1. 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).
2015年：
1. 张升, 顾汉洋, 陈宇清, 周肖佳, 刘刚, 竖直环管内自然对流现象的试验和数值研究, 核动力工程, 2015, 36(01): 14-17.
2. 张升, 顾汉洋, 驱动杆位置对控制棒驱动机构轴向传热特性的影响, 核科学与工程, 2015, 35(03): 439-444.
3. 周肖佳, 王丰, 刘刚, 林绍萱, 毛飞, 詹阳烈, 张升, 顾汉洋, 控制棒驱动机构传热机理与隔热套性能研究, 原子能科学技术，2015, 49(12): 2245-2250.
2014年：
1. 张升, 顾汉洋, 控制棒驱动机构轴向传热特性试验与理论分析,原子能科学技术， 2014, 48(11): 1992-1997.
2011年：
1. 尤园江，张升，牛风雷，非能动安全壳内大分层空间混合过程整体模拟的比例分析，中国核学会2011年学术年会论文集第3册（核能动力分卷下），中国贵州贵阳，2011-10-11.