Also others have used similar approaches
https://www.researchgate.net/post/What_is_the_characteristic_length_of_the_annular_region_of_a_concentric_cylinder
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/
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...
I am currently setting up a simulation for thermal hydraulic analysis of an AGR fuel bundle. However, the walls in this type of reactor, have a specific roughness that promototes turbulence which in turn provides better heat transfer characteristics. I am struggling to find data online to...
okay cool, thanks once again.
There is also work being done is coarse grid CFD as as a means to fill the gap between the existing but limited sub channel codes and highly detailed but time consuming 3D CFD models. It generally works by extracting a representative part of the mesh model from a...
Hi everyone, I am researching how numerical simulations have evolved over the years in nuclear reactors for assessing the thermal hydraulics inside the reactor core.
I have found vague information in regards to the three different main numerical techniques but want to learn more.
So far...