Monte Carlo N-Particle Transport Code [MCNP] is a software package for simulating nuclear processes. It was developed and owned by Los Alamos National Laboratory. It is used primarily for the simulation of nuclear processes, such as fission, but has the capability to simulate particle interactions involving neutrons, photons, and electrons. MCNPX was also developed at Los Alamos National Laboratory, and is capable of simulating particle interactions of 34 different types of particles (nucleons and ions) and 2000+ heavy ions at nearly all energies [1], including those simulated by MCNP. Both codes can be used to judge whether or not nuclear systems are critical and to determine doses from sources, amongst other things.
   | Radiation Safety Information Computational Center - RSICC Home Page |
| | LANL MCNPX website - MCNPX home Page |
| | LANL MCNP-5 website - Los Alamos National Laboratory: MCNP Home Page |
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