Encourages questions and exploration.
Professor Shuisheng He is a Professor of Thermofluids in the School of Mechanical, Aerospace and Civil Engineering within the Engineering faculty at the University of Sheffield, where he joined as Chair in Thermofluids in March 2011. In March 2026, he was appointed as the United Kingdom Atomic Energy Authority (UKAEA) Chair in Fusion Technology, focusing on engineering challenges in fusion power plant design through collaboration with UKAEA's thermal hydraulics and modelling teams. He graduated from Huazhong University of Science and Technology in China with BSc and MSc degrees in thermal power engineering, followed by a PhD in 1992 from the Nuclear Engineering Research Group at the University of Manchester. After six years of post-doctoral research at Manchester, he served over three years as an analyst in British Energy’s reactor thermal hydraulics team. He returned to academia in 2002 as a lecturer and later reader at Robert Gordon University, then advanced to senior lecturer in 2005 and reader in 2008 at the University of Aberdeen. A Chartered Engineer and Fellow of the Institution of Mechanical Engineers, he currently serves as Course Director for the Nuclear Engineering Programme.
Shuisheng He’s research centers on fluid mechanics and heat transfer, combining computational fluid dynamics with experimental investigations. His interests encompass nuclear reactor thermal hydraulics, fundamental studies of turbulence, flow transition, and drag reduction, with extensions to fusion thermal hydraulics and carbon capture and storage. He leads the Heat, Flow and Turbulence Research Group (HeFT), contributing to projects including Sub-channel CFD for nuclear fuel bundles, liquid metal heat transfer in fast reactors, buoyancy-driven flows in high-temperature gas reactors, and supercritical water reactors under ECC-SMART (H2020). Funding sources include EPSRC, BEIS, US DOE, and industry partners like EDF. Key publications feature 'Simulations of thermal stratification during thermal transients in a test facility for sodium-cooled fast reactors' (Nuclear Engineering and Design, 2025), 'Prediction of heat transfer deterioration due to buoyancy' (International Journal of Heat and Mass Transfer, 2025), 'Impact of conjugate heat transfer on the turbulence and heat transfer in an upward heated pipe flow at supercritical pressure' (International Journal of Heat and Mass Transfer, 2024), 'LES of the upper plenum of the liquid metal fast reactor under the forced flow conditions' (Nuclear Engineering and Design, 2024), and 'Turbulence enhancement in body force opposed flows' (Physical Review Fluids, 2024). His contributions bridge academia and industry, advancing safety and efficiency in nuclear and fusion technologies.