How to deal with MCNP stack overflow

[scu-mxy]

TL;DR

Before I change the neutron cross section library, the program can run normally. So I believe My input file is fine. I have used MPICH to speed up the calculation. My computer has 16G RAM, how can I solve this problem

 

[Alex A]

Are you using the ASCII version of the library or the binary version? What library?

If your library is too new, it can crash older versions of the code. New features (tables) in the libraries can lead to weird even negative indices into the cross section data. Memory access is then attempted outside the program space. I've not seen this explicitly with 5. I learned my lesson with 4.