Can openmoc program calculate fuel element plates?

[Jialiang Nie]

Hello everyone, I have been looking for many examples related to OpenMOC, but I haven’t found any concerning plate-type fuel elements. This is a single plate-type fuel element that I built using the OpenMOC program, but I always encounter kernel crashes, which I believe is due to issues in the geometric modeling. Additionally, if the rectangle is drawn as a flat source region, it is obviously non-uniform. So, how does OpenMOC address the issue of drawing a flat source region for plate-type fuel elements? Could someone help me check this? Thank you very much.

[Guillaume Giudicelli]

Hello

OpenMOC can handle plate geometries, because you can describe them using quadratic (here linear) shapes.

I believe you are hitting this error because of an error in the definition of the fuel geometry. 

The fuel (plate_cell ?) should be +1 (above) for the bottom plane and -1 for the top plane (below this plane)

Note that the moderator cell region definition is also problematic. The way you defined it, it's the intersection of all these half spaces which is actually null.

I think OpenMOC should be able to let you define the region as a union, though I have not done it in a while.

If it can't, then use 4 cells for the moderator 

In the future you will want to paste the script rather than screenshots of the script.

Best,

Guillaume

[Jialiang Nie]

Thank you very much for your detailed answer. I have made detailed modifications. Please allow me to ask a few more questions. I am verifying the few-group cross-sections output by OpenMC for OpenMOC verification. However, the results differ greatly, one is 1.5 and the other is 0.08. I have carefully checked the cross-section values as well as the geometry, is it a problem with the flat source region division? OpenMOC seems to have poor uniformity in drawing flat source regions for rectangular programs. Can you help me ? Thank you very much.