hi all
I have this model of the pin cell of ORP 1000 Benchmark.
It can’t run and an error was reported.
The files attached are ORP 1000 specification , the input files ,and the error report.
Thank you very much for your help.
geometry.xml (4.01 KB)
materials.xml (1.91 KB)
plots.xml (172 Bytes)
settings.xml (391 Bytes)
Good morning,
In OpenMC, the root universe does not need to be given an id of 0 like in other codes (e.g., MCNP). Instead, OpenMC determines from the input which universe is the root, or “real world.” Since this input has multiple universes that are not nested below other universes, OpenMC cannot tell which is supposed to be the real root universe.
To make this particular model work, you can just comment out the pin-cells in the “pin-cell construction” section that are not part of Universe 3. This way, OpenMC will be able to decipher that universe 0 is your root.
Hope this helps!
Adam
