NDLI: Thermal-Hydraulic Study of Wire-Wrapped Blanket Assembly of CEFR

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Liu, Yang Yu, Hong Liu, Yizhe
Copyright Year	2013
Abstract	The blanket assemblies of China Experimental Fast Reactor (CEFR) were specially designed for the purpose of fuel breeding. There are two parts of the blanket assembly that have significant influence on its thermal-hydraulic feature: the labyrinth throttle set and the wire-wrapped fuel bundle. In this paper, the flow and temperature distribution of sodium coolant in fuel bundle, as well as the pressure drop in the labyrinth throttle set were investigated by solving the three-dimensional conservation equations of mass, momentum and energy, for a wide range of Reynolds number. Different turbulent models: k-ε, SST and Reynolds stress model (RSM) were used and compared with experimental correlations in the study of fuel bundle. The cross flow strength in three typical sub-channels and the influence of steer rods were also investigated. It has been found that the SST model fits best with the experimental correlation and although dampened the cross flow in edge channel, the steel rods installed in the hexagonal duct could enhance the heat transfer by “pushing” the sodium coolant to inner channel of the fuel bundle. Moreover, the relationship between the slot width of the labyrinth throttle set and the pressure drop under different coolant mass flow rate was analyzed, and found out the slot width that satisfied the design requirement of the blanket assembly.
Sponsorship	Nuclear Engineering Division
File Format	PDF
ISBN	9780791855799
DOI	10.1115/ICONE21-15739
Volume Number	Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors
Conference Proceedings	2013 21st International Conference on Nuclear Engineering
Language	English
Publisher Date	2013-07-29
Publisher Place	Chengdu, China
Access Restriction	Subscribed
Subject Keyword	Temperature distribution Turbulence Ducts Reynolds number Momentum Rods Wire Fuels Steel Flow (dynamics) Stress Design Cross-flow Sodium Pressure drop China Fast neutron reactors Coolants Manufacturing Heat transfer
Content Type	Text
Resource Type	Article

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