A code package to produce ACE-formatted files for MCNP calculations.
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Updated
Dec 2, 2022 - Fortran
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 code package to produce ACE-formatted files for MCNP calculations.
Created by Los Alamos National Laboratory