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 …

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 …

In this paper, Eulerian two-phase model coupled with wall boiling model was employed to
simulate the departure from nucleate boiling (DNB) in a 5× 5 fuel assembly. The numerical …

The wire-wrapped tight lattice fuel assembly is one of the options for small modular reactors.
To investigate the performance of this assembly, the subcooled boiling characteristics in a …

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 …

A high pressure critical heat flux (CHF) facility was built at the University of Wisconsin-
Madison to investigate the CHF phenomena in rod bundles under lower mass flux and high …

To improve the heat transfer efficiency of the reactor fuel assembly, it is necessary to
accurately calculate the two-phase flow boiling characteristics and the critical heat flux …

To determine the safe boundary of fuel assembly operation and improve the heat transfer
performance of fuel assembly, it is necessary to accurately calculate the thermohydraulic …

CFD methodology for subcooled flow boiling is significantly affected by the heat flux
partitioning model, which plays a crucial role in predicting the mass source term generated …