Help debugging MCNP code - particle lost and zero latice element found
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SUMMARY
The discussion focuses on troubleshooting a particle lost error in MCNP code, specifically related to geometry errors in the lattice. Users are advised to utilize the interactive plotter feature in MCNP, accessed via the command line with the command "mcnp5 ip inp=file". The issue arises from improper cell definitions, particularly with cell 99, which is identified as a void cell. Recommendations include redefining the reflectors with simple surfaces to facilitate correct void cell definition.
PREREQUISITES- Familiarity with MCNP (Monte Carlo N-Particle Transport Code) version 5
- Understanding of 3-D geometry modeling and cell definitions
- Knowledge of using the interactive plotter feature in MCNP
- Basic command line operations for executing MCNP commands
- Review the MCNP manual for detailed instructions on using the interactive plotter
- Learn how to define cells and surfaces correctly in MCNP
- Explore best practices for troubleshooting geometry errors in MCNP models
- Investigate the implications of using macrobody surfaces versus simple surfaces in MCNP
MCNP users, nuclear engineers, and researchers involved in particle transport simulations who need to debug geometry-related issues in their models.
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