MCNP

Description

MCNP is a general-purpose Monte Carlo N-Particle code that can be used for neutron, photon, electron, or coupled neutron/photon/electron transport. Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, Detector Design and analysis, nuclear oil well logging, Accelerator target design, Fission and fusion reactor design, decontamination and decommissioning.

Required Modules

Serial

intel
mcnp

Parallel (MPI)

intel
openmpi
mcnp

System Variables

DATAPATH

PBS Script Examples

See the MCNP_PBS page for mcnp PBS script examples.