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MCNP
The Monte Carlo N-Particle (MCNP) radiation transport code is a Monte Carlo transport code developed by Las Alamos National Laboratory (LANL).
It supports over 37 different types of particles, and is widely used by nuclear engineers,
and nuclear physicists.
Here are 2 public repositories matching this topic...
Compare ENDF nuclear data processed by NJOY and FRENDY into ACE format with visual cross-section analysis.
ace comparison nuclear serpent cross-sections dataprocessing njoy mcnp cross-section endf openmc frendy njoyfrendycomparison compared nucleardataprocessing tendl
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Updated
Jul 14, 2025 - Shell
Created by Los Alamos National Laboratory
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- Website
- github.com/topics/mcnp
- Wikipedia
- Wikipedia