Publikationsrepositorium - Helmholtz-Zentrum Dresden-Rossendorf
1 PublikationA comprehensive review of numerical and experimental research on the thermal-hydraulics of two-phase flows in vertical rod bundles
Abstract
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-phase flow hydrodynamics and heat transfer in nuclear fuel assemblies. A comprehensive review of experimental and CFD methods used in the last 30 years to analyse the thermal-hydraulic characteristics of sub-channels in rod bundle geometries under different flow conditions (adiabatic and boiling two-phase flow) is presented. The effects of design parameters, e.g. rod-pitch length, mixing vane angle, and flow parameters, e.g. pressure, mass flux and heat flux, on flow hydrodynamics and heat transfer performance are summarized. In addition, the capabilities of CFD modelling of two-phase in rod bundles are discussed. Moreover, based on the existing studies, some recommendations for future studies are given.
Keywords: Rod bundle; CFD; Experimental study; Two-phase flow; Flow hydrodynamics; Heat transfer
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International Journal of Heat and Mass Transfer 221(2024), 125053
Online First (2023) DOI: 10.1016/j.ijheatmasstransfer.2023.125053
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- Zweitveröffentlichung erwartet ab 26.12.2024
Permalink: https://www.hzdr.de/publications/Publ-37339