How to deal with MCNP stack overflow

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SUMMARY

The discussion focuses on handling stack overflow issues in the MCNP (Monte Carlo N-Particle Transport Code) when using different library versions. Users are advised to choose between the ASCII and binary versions of the library, as newer libraries can cause crashes in older MCNP versions due to new features like tables. Specifically, negative indices into cross-section data can lead to memory access violations. The issue has not been observed with MCNP version 5, but caution is advised based on experiences with version 4.

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  • Understanding of MCNP (Monte Carlo N-Particle Transport Code)
  • Familiarity with library versions and their compatibility
  • Knowledge of memory management and access violations
  • Experience with cross-section data in particle transport simulations
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  • Research compatibility issues between MCNP versions and library updates
  • Learn about memory access violations in programming
  • Explore the differences between ASCII and binary library formats
  • Investigate best practices for managing cross-section data in MCNP
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Researchers, physicists, and software developers working with MCNP simulations, particularly those troubleshooting stack overflow issues related to library compatibility.

scu-mxy
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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
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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.
 
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