Recent content by Meb15aa

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...

Thank you for the reply I found online that the rib height is 0.11 inches which somewhat matches the second reference you provided. Thanks again

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...

Thank you for the reply Astronuc, very useful information.

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...