A high-fidelity, free user input cylinder meshing tool for MCNP.
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Updated
Jun 6, 2021 - C
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.
A high-fidelity, free user input cylinder meshing tool for MCNP.
Created by Los Alamos National Laboratory