Tenglong Cong

Shanghai Jiao Tong University — China

Engineering · Physical Sciences

23h-index1.7kcitations122works3.12yr avg
OpenAlex↗ORCID↗Google Scholar↗Lab page↗

Accepting Students?

No reports yet. Know if this professor is taking students?

Research Topics

Nuclear Engineering Thermal-Hydraulics(44), Nuclear reactor physics and engineering(43), Nuclear Materials and Properties(38), Heat Transfer and Boiling Studies(37), Heat transfer and supercritical fluids(37)

Publications122 total

A sensitivity analysis and computational assessment of topology optimization heat sink channel using a power law model
International Journal of Thermal Sciences·2026
CFD investigation of critical heat flux in full-length 5 × 5 rod bundles with simple support spacer grids: model validation and thermal-hydraulic analysis
Applied Thermal Engineering·2025
Calculation Simulation of Equivalent Thermomechanical Properties of Dispersion Nuclear Fuel
Materials·2025Open Access
Computational study of MHD tri-hybrid $$\left( {Al_{2} O_{3} + CuO + TiO_{2} } \right)/H_{2} O$$ nanofluid flow between disk and cone with the effect of thermal radiation
Journal of Thermal Analysis and Calorimetry·2025
Theoretical and numerical investigations of dislocation evolution and anisotropic plasticity in UO2
International Journal of Plasticity·2025· 1 cited
Experimental and numerical analysis of a non-nuclear heat pipe space reactor prototype
Applied Thermal Engineering·2025· 1 cited
Numerical simulation of the effect of micro-layer slopes on bubble growth and heat transfer during nucleate pool boiling
Progress in Nuclear Energy·2025· 1 citedOpen Access
Numerical research of flow and heat transfer characteristics of high-Prandtl-number fluoride salt in the pebble bed channel
Progress in Nuclear Energy·2025· 1 cited
Modeling of the multi-scale related thermo-mechanical coupling behaviors in a helical cruciform fuel assembly
Nuclear Engineering and Design·2025
Investigation on coupling methods for heat transfer field between a reactor core and heat pipes
Annals of Nuclear Energy·2025
Numerical study of boiling crisis characteristics in helical cruciform fuel with axially non-uniform power distribution
Annals of Nuclear Energy·2025· 2 cited
A numerical study on single-phase heat transfer characteristics of the helical cruciform fuel assembly
Progress in Nuclear Energy·2025· 1 cited
Development of a new onset of film boiling model within the fouling layer
Annals of Nuclear Energy·2025· 1 cited
Code development and initial safety analysis of a mega-power heat pipe-cooled reactor coupling with the Brayton energy conversion system
Applied Thermal Engineering·2025· 4 cited
Study on dryout characteristics in a 3-rod tight-lattice bundle
Progress in Nuclear Energy·2025
Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor
Nuclear Engineering and Technology·2025· 3 citedOpen Access
Subchannel analysis of post-dryout flow and heat transfer in a tight-lattice fuel assembly
Annals of Nuclear Energy·2025
Numerical simulation of the fluoride salt flow and heat transfer in the pebble bed under pulsating flow conditions
Applied Thermal Engineering·2025· 2 cited
Numerical simulation of impurity particles migration and deposition within the 5 × 5 fuel assembly under nucleate boiling conditions
Annals of Nuclear Energy·2024· 3 cited
A reduced cluster dynamics modeling of radiation damage in tungsten
Nuclear Materials and Energy·2024· 1 citedOpen Access
page 1 of 7Next →

Frequent Co-authors

Hanyang Gu(15), G.H. Su(13), Suizheng Qiu(13), Wenxi Tian(12), Yao Xiao(11), Minjun Peng(9), Xiang Zhang(7), Genglei Xia(6), Junlong Li(4), Rui Zhang(4), Rui Zhang(3), Mengke Cai(3), Zhigang Zhang(3), Haisu Du(3), Hui Guo(2), Maolong Liu(2), Yao Xiao(2), Qi Zhang(2), Bicheng Wang(2), Rui Zhang(2)