Difference between revisions of "MCNP"
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Revision as of 17:44, 14 December 2016
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/2013
- mcnp
Parallel (MPI)
- intel/2013
- openmpi
- mcnp
System Variables
- DATAPATH