i am relatively new to Openmc. I created the attached geometry for a reactor. However, i noticed that when i viewed the geometry, the hole cells i filled with another universe appears as empty. Please what am i doing wrong and how can i fix this?
Hi AsukuA, welcome back to the openmc community
I have checked your input and I think this model is quite complicated so I didn’t resolve it properly since I think you are the one who knows how you want to model your geometry.
But I have updated some parts that might help you localize your problem.
One thing that I noticed is you think the CSG model in openmc will change the region being filled with previous cell material to the newly defined cell material, so I am detecting many cell overlaps in your model.
I think you need to know that each cell should not intersect the other cells. You can create a universe that intersects others (but is still made up of its corresponding cells) because the universe will become a filler of another cell that has a region, which again, shouldn’t be intersecting other cell’s regions.
This was some part of your script that I modified, so when you said that your cell was outside of the cell, then you can just add ~regions_...
update: I am modifying your first diameter parameter in your ring_radii array from 1.095 to 1.195 because this water region has a smaller radius compared to the guide tube radius 0.595 cm (1.19 cm diameter) ring_radii = np.array([0, 1.195, 2.19, 3.285, 4.38, 5.475, 6.57, 7.665, 8.76, 9.855, 10.95])
Also, you need to add a region to cover all your core and add the boundary condition to the outer surface. So, I added a test cell to make sure that the model is in good shape up to those parts of notebook cell. you need to check again for other cell outside of your fuel configuration because the keff is low for current model
Hi, Wahidlfti
thank you so much for your support. The modifications you have made were very helpful. The core regions is now exactly how i wanted it.
However, the core is suppose to fit in an annular berylium reflector and there is a lower berylium reflector below it. The problem is that when i use the fuel bundle you modified and try to add it to the reflector it penetrates the bottom berylium (see attached photo).
i easily do this in SCALE Monte carlo code by just creating a hole of same size as the fuel bundle in the annular Berylim universe and
fill that hole with the fuel bundle. But is proving difficult in openmc.
in SCALE I can also create a central hole in the fuel bundle and then place a control_rod universe/cell inside it. That way i do not have to include the central control rod in the bundle cell/universe.
Also notice that i created a hole to the right of the annular berylium reflector and filled it with a material. when i try to fill it with a universe (irc_universe) the universe doesnt show. it appears empty.
finally observe that the bundle universe intersect the shim tray on top of the annular berylim reflector also without excluding it.
once again, i am very grateful for your kind contributions.