Recent progress of CFD applications in PWR thermal hydraulics study and future directions

M Wang, Y Wang, W Tian, S Qiu, GH Su - Annals of Nuclear Energy, 2021 - Elsevier
CFD method has the potential to simulate the detailed three-dimensional flow and heat
transfer features in nuclear reactors, and is promising to play a more important role in the …

Numerical study on the boiling heat transfer and critical heat flux in a simplified fuel assembly with 2× 2 helical cruciform rods

T Cong, Y Xiao, B Wang, H Gu - Progress in Nuclear Energy, 2022 - Elsevier
The helical cruciform fuel was potential to upgrade the core power density while maintaining
the safety margin of a reactor. However, the detailed analysis on the boiling phenomena …

Numerical analysis on subcooled boiling in PWR coolant channel based on a modified multi-scale interface model

X Zhang, R Li, M Peng, T Cong, C He, G Xia… - Applied Thermal …, 2023 - Elsevier
A modified multi-scale interface model was employed with the Eulerian two-fluid framework
to investigate the three-dimensional characteristics of subcooled boiling characteristics in a …

Numerical investigation of flow boiling characteristics in narrow rectangular channels using two-fluid Eulerian CFD model covering a wide range of pressures

J Han, W He, Y Liu, D Gao, C Zhao, H Bo - Applied Thermal Engineering, 2024 - Elsevier
Narrow channel heat exchange technology is one of the key technologies for the
development of integrated small modular reactors (SMR). The 'wall heat flux …

Numerical simulation of boiling two-phase flow in the subchannel under static state and rolling motion

Y Li, W Li, L Wan, Y Xi, N Wang - International Journal of Heat and Mass …, 2020 - Elsevier
The design and operation of the offshore floating reactor cannot follow those of the land-
based reactor affected by the complex marine environment. This study investigated …

A comprehensive review of numerical and experimental research on the thermal-hydraulics of two-phase flows in vertical rod bundles

S Taş - International Journal of Heat and Mass Transfer, 2024 - Elsevier
Thermal-hydraulic analysis of two-phase flow plays a crucial role in the optimal design of
nuclear fuel assemblies and in nuclear safety. This paper presents the state of the art in two …

A review on the external cooling of the pressure vessel lower head in nuclear power plant

Y Hou, R Cai, X Huang, C Zhang, W Li, B Cai… - … Engineering and Design, 2023 - Elsevier
At the beginning of the new century, since nuclear energy received widespread attention
due to its economy and environmental protection, the nuclear industry has developed …

A modified wall boiling model considering sliding bubbles based on the RPI wall boiling model

J Shi, R Zhang, Z Zhu, T Ren, C Yan - … Journal of Heat and Mass Transfer, 2020 - Elsevier
The bubble sliding is an important phenomenon in subcooled boiling flow, which has a
significant influence to heat transfer, while the RPI wall boiling model does not consider the …

Numerical investigation of the effect of mixing vanes on subcooled boiling in a 3× 3 rod bundle channel with spacer grid

P Yang, T Zhang, L Hu, L Liu, Y Liu - Energy, 2021 - Elsevier
Mixing vane grids (MVGs) are an integral part of nuclear reactor fuel assembly, and
significantly impact the flow and heat transfer characteristics of the coolant in a rod bundle …

Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model

T Cong, R Zhang, L Chen, X Zhang, T Yu - Annals of Nuclear Energy, 2018 - Elsevier
An improved wall boiling model with consideration of thin film heat transfer was employed
with the Eulerian two-fluid model to investigate the three-dimensional flow boiling …