Openmc aborted unexpectedly..how do i solve this?

[Pranto]

@Mashaba

the power of the reference reactor is 200MW…when i use this as the power the kernel dies

@Mashaba My guess, you’re running out of memory when data is being loaded. triso-burnup notebook file

@Mashaba

but i am still getting those negative densities as given bellow for many isotopes…

Paul already answered this question in another post.

Warning while reading from ENDF/B-VII.1

These are both data-related issues. Probability tables are used for unresolved resonance region cross sections to account for energy self-shielding effects. These tables are generated by NJOY and should not have negative probabilities, but this does sometimes occur. OpenMC will zero out those values, but it is telling you that the data produced by NJOY may be suspect. The second message about the maximum neutron energy is due to an erroneous evaluation of Be7 in ENDF/B-VII.1 that has an upper l…

Hope this will help!