How to deal with MCNP stack overflow

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The discussion centers on the use of ASCII versus binary versions of a specific library, highlighting potential compatibility issues with older code versions. New features in libraries, such as tables, can cause unexpected negative indices in cross-section data, leading to memory access violations. Users have experienced crashes when using newer libraries with older code, particularly noted with version 4. There is a cautionary note regarding the stability of version 5, although no explicit issues have been reported yet. Compatibility and memory management are critical considerations when updating libraries.
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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
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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.
 
Thread 'Creating the geometry using MNCPX VisEd'

Thread 'Creating the geometry using MNCPX VisEd'

I'm working on the MSFR design and want to calculate keff. I'm trying to use the MNCPX VisEd program included with MCNP 6.1 to create my geometry. The reactor I'm designing doesn't contain fuel rods or moderator structures. The molten salt fuel circulates within the cylindrical reactor core. I'm having problems creating the geometry using MNCPX VisEd. VisEd allows for easy drawing of nested sphere, cylinder, or rectangular prism cells. However, when you want to draw a torus section within...
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