"Y plus" calculator value for a fuel bundle

AI Thread Summary
The discussion focuses on using an online Y plus calculator to determine the Y plus value for a fuel bundle, specifically addressing the appropriate reference length. Participants confirm that utilizing the hydraulic diameter, calculated as 4A/P (where A is the cross-sectional area and P is the wetted perimeter), is a valid approach. The reference length is crucial for converting the fuel rod bundle into an equivalent pipe flow for easier analysis. Additional insights highlight the differences between PWR and BWR fuel assemblies, emphasizing the complexity of flow dynamics due to structural elements like spacer grids and water rods. Understanding these factors is essential for accurate calculations in fluid dynamics related to nuclear engineering.
Meb15aa
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Hi everyone,
I am using a online y plus calculator to work out the y plus value for a fuel bundle.
http://www.pointwise.com/yplus/

In regards to the reference length, I have been told by peers to utilise the hydraulic diameter using 4A/P
where A is the cross sectional area, and P is the wetted perimeter.
Is this correct or is there any other better ways to undergo this.
Thank you in advance
 
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Meb15aa said:
In regards to the reference length, I have been told by peers to utilise the hydraulic diameter using 4A/P
where A is the cross sectional area, and P is the wetted perimeter.
Is this correct or is there any other better ways to undergo this.
For the calculator in question, if the reference length, L, is described by the hydraulic diameter, then yes, it is correct to use it as mentioned. Does the calculator documentation discuss or describe the 'reference length'? In other words, how is the 'reference length' defined?

CFD-online has the following discussion on turbulence scale length.
https://www.cfd-online.com/Wiki/Turbulent_length_scale
 
Also others have used similar approaches
https://www.researchgate.net/post/What_is_the_characteristic_length_of_the_annular_region_of_a_concentric_cylinder
 
Meb15aa said:
the reference length is used to convert the fuel rod bundle into an equivalent pipe flow that is easier to analyse

https://www.nuclear-power.net/nuclear-engineering/fluid-dynamics/internal-flow/hydraulic-diameter-2/
So one wants to determine the reference length of an assembly as opposed to the subchannels in the lattice?

Bear in mind that PWR assemblies have uniform arrays, more or less, with spacer grids, and guide tubes may have some flow if not blocked by thimble plugs. Spacer grids in the active core are made of Zr-alloy and have mixing vanes, and some assemblies have mid-span mixing grids, which are shorter (in height) than the structural grids.

BWR fuel assemblies used to be more uniform, with one or two water rods which also served to fix the spacer grids. Nowadays, BWR rods have two groups of part-length rods (different lengths) that terminate in the core, and water channels that are round, square or cruciform.
 
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