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 …

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 …

Flow boiling heat transfer tests were conducted to evaluate the Critical Heat Flux (CHF) and
Heat Transfer Coefficient (HTC) of conventional and accident tolerant fuel (ATF) cladding …

Abstract The Critical Heat Flux (CHF) is crucial for the safety of power equipment working
with boiling heat transfer, such as the heat exchanger and fuel assembly. The wall heat …

CFD method enables high-fidelity investigation of complex systems. Numerous sensitivity
studies on boiling sub-models improve the applicability and reliability of the multiphase-CFD …

This paper aims to see how well the open-source CFD code OpenFOAM can simulate the
critical heat flux (CHF) in vertical pipe under extreme conditions, close to PWR operating …

The helical structure of the petal-shape fuel element results in a high heat transfer
performance. Therefore, it is crucial to analyze its thermal–hydraulic characteristics …

Due to the advantages of flexibility, security and economy, small modular reactor (SMR) has
become a research hotspot in the field of nuclear energy. Gas liquid two-phase flow is one of …

The thermal–hydraulic analysis of coolant flow in the reactor core plays a significant role in
the optimized design of nuclear fuel assemblies and nuclear safety. This article reviews the …

This paper uses Eulerian multiphase computational fluid dynamics (MCFD) simulations to
predict the critical heat flux in a simplified CANDU test geometry for typical pressurized …