Monte Carlo N-Particle Transport Code

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 critical and to determine doses from sources, amongst other things.

See also

• FLUKA Particle Transport Code
• Nuclear engineering
• Monte Carlo method
• Nuclear reactor
• Neutron
• MELCOR
• Geant4
• MONK
• KENO
• MCU